ML20210F827
| ML20210F827 | |
| Person / Time | |
|---|---|
| Site: | 07001869 |
| Issue date: | 04/05/1985 |
| From: | Mcgee C RADIATION MANAGEMENT CORP. (RMC) |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20210F766 | List: |
| References | |
| 03626, 3626, RR01APR85.NRC, RR1APR85.NRC, NUDOCS 8604020280 | |
| Download: ML20210F827 (148) | |
Text
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p L I C f:M E NO. S N M -- 15 2 4 RR01APR85.NRC (PAGE 1 0F 147)
RMC Radiation Management Corporation. 3440 Market St., Philadelphia, PA 19104 (215) 243-2950 DIRECTOR OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS U.S.
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C.
20555 GENTLEMEN:
RADIATION MANAGEMENT CORPORATION (RMC) hereby reauests renewal of SNM-1524 which expires April 30, 1985.
Information specified in.10 CFR 70.22(a) follows:
(1)
Incorporated in the State of Pennsylvania.
UPrincipaih0f.ficeO RADIATION. MANAGEMENT CORPORATION Rcom'320
~3440' MARKET STREET.
PHILADELPHIA, PA.
19104 Principal Officers:
All are cittrens of U.S.A.
A.
RADIATION NANAGEMENT CORPORATION ONE STATE STREET REGO'.G CY LTMG j MERIDEN, CT.
04450 s
' Date '
G [!
Richard T.
He Kernan President &
Log.
Chief Executive Officer
,J,,,.
Robert C.
Kane cri. To.
2 j Action Compi..(/....T.
~~
Treasurer Frazier L.
Bronson Vice-President l
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D.
RADIATION MANAGEMENT CORPORAf!ON g.
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Room 320 g
.g/
3440 MARKET STREET J
jg%g A ;(J f PHILADELPHIA, PA.
191.04
-h Ro.1er E. L i n n e,ria n n,
M.D.
N Corporate Senior Vice-President Dernard T. Geenan, Secretarv There is no control or ownership exercised ever Radiation 0362G
~
Manadement Corecrotton bw a r. v alien, foreign corporation or foreign scvernment.
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LIdhdSE NO. SNM-1524
'^
RR29NAR85.NRC (PAGE 2 0F 147)
_[_
(2)
The material is to be used for instrument calibration (including lung counters); as tracers incidental to sample analvsisi and Possession / Processing incidental to the Onalvsis of bioassaw, environmental, in-Plant-and/or any other sample twee/catesors within the listed Possession limits.
Samples will normalls be Possessed, stored and Processed at RMC's facilities at 3440 or 3508 Market Street, Philadelphia, Pa.
However, Possession, storase and use incidental to the Performance of activities at temPorarv Job sites and at any other use site authorized bw our BwProduct Material License No. 37-13129-01 is also reouested.(See ATTACHMENT 41)
(3)
The license is reouested for the maximum Period of issuance.
(4)
SPecial Nuclear Chemical and/or Maximum amount that Material Physical form licensee mas Possess at anw one time
===
===
=n======
Plutonium --
Anw 0.9 grams total, Anw Isotope 200 microcuries of anw isotope, no single source to exceed 10 microcuries.
Uranium-235 Anu 10 grams total.
'Anw 10 microcuries total.
============================================a=======
(5)
Reserved.
t (6)
Radiation Management Corporation has been involved in Perform-ins radioactivity measurements for more than fifteen wears and has been Performing Lung Countins for Uranium and measurements on samples contains SPecial Nuclear Material for ten wears.
SPecial Nuclear Material will be used bv or under the super-vision of Roger E.
Linnemann, Charles E.
NcGee, Frazier L.
Dronson, Lee Booth,' James D.
Gibs'on, John P.
Andrews, Wawne D.
Vogel, Larrw F. Umbaugh and/or other individuals approved to work with radioactive materials under our Burroduct Material L2 cense No. 37-13129-Or.
Resumes outlining the cualification, training and enPerience of the individuals named above are included in ATTACHNENT #2.
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rm. Stan-1 Y A
'd RP29Iw2SS.NRC (PAGE 3 0F 147)
FW KRMC (7)
A summary of FACILITIES AND EQUIPMENT cooled from our recent Bueroduct Material License renewal reuvest is included and therefore is labeled as ATTACHMENT #6.
The ouantity of Special Nuclear Material that will.be possessed precludes'the necessistu for a criticality accident alarm system.
(8)
A sum.marv of our RADIATION StFETY PROGRAM conied from our recent Burroduct Materia] License renewal reauest is included and therefore is labeled as ATTACHMENT 67.
No mention of criticalitu is included in these procedures es the minimal amount to be Pocsessed precludes this he:Ord.
Please note that. Charles E.
He Gee is now the Radiation Safets Officer for RMC.
His resume is' included in ATTACHMENT #1.
I am aware that this renewal reouest is marsinalls late.
I had Planned to submit a termination reauest, however I Just became aware that we are in the possession of small amounts of enriched U-233 and U-235 that is used in the calibration of Lund Counters which Precludes our termination of this license.
Therefore, I reauest an execPtion to the 30 das erior to expiration rule for consideration for timeli tiling of renewal reouests.
If this is not possible please consider this as a formal reouest for POSSESSION AND STORAGE ONLY until such time as our renewal reouest can be Processed.
The renewal fee reouired by 10 CFR Part 170.31, paracraeh 1(N) of $350.00 is enclosed.
Thank you for vour consideration of this matter.
If there are any uuestions concerning this application or if you reouire anu additional information clease contact me directiv.
Sincerelv, AR Charles E.
Mc Gee, Ph.D.
Radiation Safets Officer (215) 243-2950
Enclosures:
1.
Check No. 23449($350.00) 2.
ATTACHMENT #1 3.
ATTACHMENT 82 4.
ATTACHMENTS 16 - 410 and
- 12 - 113 of LICENSE NO. 37-13129-01 5.
ATTACHMENT #11
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LICENS SNM-1524 RR01APR85.NRC l
(PAGE 4 0F 147)
LIST OF ATTACHMENTS ATTACHMENT #1
SUMMARY
OF ITEM (2):
(PAGE 5)
ADDRESSES WHERE LICENSED MATERIAL WILL BE USED OR POSSESSED.
ATTACHMENT #2
SUMMARY
OF ITEM (6):
(PAGE 6-27)
RESUMES FOR INDIVIDUALS AUTHORIZED TO WORK WITH SPECIAL NUCLEAR MATERIAL ATTACHMENT #6
SUMMARY
OF ITEM 9 (PAGE 50-73)
FACILITIES AND EQUIPMENT.
(PAGE 28-51)
ATTACHMENT #7
SUMMARY
OF ITEM 10:
(PAGE 74-162)
RADIATION SAFETY PROGRAN.
(PAGE 52-140)
ATTACHMENT 88 ITEM 11:
WASTE MANAGEMENT.
(PAGE 163)
(PAGE 141)
ATTACHMENT 99 INFORMATION SPECIFIC TO MEDICAL SERVICES (FAGE 164)
DIVISION USE AT 3440 AND 3508 MARKET STREET, (PAGE 142)
PHILADELPHIA) PA.
19104.
(Use Address A.).
ATTACHMENT #10 INFORMATION SPECIFIC TO NUCLEAR SERVICES (PAGE 165)
DIVISION (MWRO) USE AT 3356 COMMERCIAL AVENUE, (PAGE 143)
NORTHBROOK, ILL.
60002.
(Use Address B.).
ATTACHMENT til INFORMATION SPECIFIC TO NUCLEAR SERVICES (PAGE 144)
DIVISION USE AT ONE STATE STREET, MERIDEN, CT. 06450 (Use Address C.).
ATfACHMENT #12 INFORMATION SPECIFIC TO NUCLEAR SERVICES (PAGE 167)
DIVISION (NERO) USE AT 1455 SCHUYLKILL ROAD (ROUTE 724),
(PAGE 145)
POTTSTOWN, PA.
19444 AND OTHER INDICATED ADDRESSES.
(Use Address D.).
ATTACHMENT f13 INFORMATION SPECIFIC TO TEMPORARY JOB SITES (PAGE 168-169)
AND CUSTOMARY FACILITIES.
(Use Address E.).
(PAGE 146-147)
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LICENS 0.
\\--
RRO1AP
.NRC (PAGE 5 0F 147)
ATTACHMENT *1 (Pase 1 0F 1)
SUMMARY
OF ITEM (2):
ADDRESSES WHERE LICENSED MATERIAL WILL BE USED OR' POSSESSED:
A.
RADIATION MANAGEMENT CORPORATION MEDICAL SERVICES DIVISION 1.
3508 MARKET STREET PHILADELPHIA, PA.
19104 AND 2.
3440 MARKET STREET PHILADELPHIA, PA.
19104 B.
RADIATION MANAGEMENT CORPORATION NUCLEAR SERVICES DIVISION (MWRO) 3356 COMMERCIAL AVENUE NORTHBROOK, ILL..60002 C.
RADIATION MANAGEMENT CORPORATION NUCLEAR SERVICES DIVISION ONE STATE STREET MERIDEN, CT.
06450 D.
RADIATION MANAGEMENT CORPORATION NUCLEAR SERVICES DIVISION (NERO) 1.
1455 SCHUYLKILL ROAD (ROUTE 724)
POTTSTOWN, PA.
19464 AND 2.
3440 MARKET STREET PHILADELPHIA, PA.
19104 E.
TEMPORARY JOB SITES AND CUSTOMER FACILITIES
~ 1.
IN NON-AGREEMENT STATES AND 2.
IN AGREEMENT STATES NOTE!
INFORMATION IN SUBSEQUENT ATTACHMENTS IS SUB-DIVIDED FOR CROSS REFERENCE TO THIS ATTACHMENT (i.e. All items noted as A.,
B.,
...E.
aPPlV to the aePlicable use address diven in this attachment.
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L I C EN SP'")O.
SNM-1524 RR01 api...NRC i
(PAGE 6 0F 147)
ATTACHMENT 42 (Pace 1 0F 22)
SUMMARY
OF ITEM (6):
RESUMES, TRAINING AND EXPERIENCE FOR INDIVIDUALS AUTHORIZED TO WORK WITH SPECIAL NUCLEAR MATERIAL.
ITEM 3A RADIATION MANAGEHENT CORPORATION MEDICAL SERVICES DIVISION 3508 AND 3440 MARKET STREET PHILADELPHIA, PA.
19104 FULL NAME TITLE 1.
Charles E. McGee, Ph.D.
Radiation Safets Officer ESEE PAGE 8-11]
NOTE:
CORPORATE RADIATION SAFETY OFFICER AND ASSISTANT RSO FOR USE-ADDRESS 3A.
2.
Roser-E. Linnemann, M.D.
President CSEE PAGE 12-143 Medical Services
' ITEM 3B RADIATION MANAGEMENT CORPORATION NUCLEAR SERVICES DIVISION (MWRO) 3356 CONNERCIAL AVENUE NORTHBROOK, ILL.
60002 FULL NAME TITLE 1.
Lerow F.
Booth, CHP Manaser ESEE PAGE 15-17]
Hidwest Resional Office (MWRO)
Nuclear Services Division NOTE:
ASSISTANT RSO FOR USE ADDRESS 3B.
ITEN 3C:
RADIATION NANAGEMENT CORPORATION NUCLEAR SERVICES DIVISION ONE STATE STREET MERIDEN, CT.
06450 FULL HAME TITLE 1.
Frazier L.
Bronson, CHP Vice President ESEE PAGE 18-20]
NOTE:
ALTERNATE CORPORATE RADIATION SAFETY OFFICER HAND ASSISTANT RSO FOR USE ADDRESS 3C.
NOTE:
Although the Primar9 use address of each individual is as noted, use of licensed material bu each individual at other RMC use addresses or at temporarv Job sites, bu individuals listed in 3A, 3B and 3D is Permissible.
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LICENSdlhD.-SNM-1524
-RR01APR85.NRC (PAGE 7 0F 147)
ATTACHMENT *2(Cont'd)
(Pace 2 0F 22)
SUMMARY
OF.: TEM (6): (Cont'd)
RESUMES, TRAINING AND EXPERIENCE OF INDIVIDUALS AUTHORIZED-TO WORK WITH SPECI AL NUCLEAR NATERI ALS.
ITEM 3D:
RADIATION MANAGEMENT CORPORATION NUCLEAR SERVICES DIVISION (NERO) 1.
1455 SCHUYLKILL ROAD (ROUTE 724)
POTTSTOWN, PA.
19464 AND 2.
3440 MARKET STREET PHILADELPHIA, PA.
19104 FULL NAME TITLE 1.
John P.
Andrews Senior Health Phwsicist ESEE PAGE 21]
NOTE 1 ASSISTANT RSO FOR USE ADDRESS 3D.
2.
James D.
Gibson, CHCM.
Manager ESee PAGE 223 Northeast Recional Office Nucle.3r Services Division 3.
Larrw F.
Umbaugh Senior Radiochemist ESee PAGE 23-24]
4.
Wawne D..Vogel Health Phwsicist CSee PAGE 25-273
- NOTE:
Although the Primars use address of each individual is as noted, use of licensed material bw each individual at other RMC use addresses or at temPorarv Job sites, bw individuals listed in 3A, 3B and 3D is Permissiblee
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O LICENSu_ 0.
SNM-IF74 RR01APR85.NRC (PAGE 8 0F 147)
ATTACHMENT D2(Cont'd)
(Page 3 0F 22)
CHARLES.E. NC GEE, PH.D.
SENIOR CONSULTANT RADIATION MANAGEMENT CORPORATION MEDICAL SERVICES DIVISION As Senior Consultante Dr. McGee is responsible for the technical direction of' activities related to the application of radioanalvtical peasurements and data interpretation.
Prior to this Positiont he Was responsible-for the management of all technical and operational functions of the analvtical laboratories in Philadelphia, PA.
During 19817 Dr. McGee served in the Position of Director of Technical Marketing Providing and imPortant technical liaison between the business and technical aspects of RMC's marketing efforts.
In 1978, Dr. McGee assumed the duties of Manager of Consultind and Analvtical Laborators Services.
He was responsible for the operation of the counting laboratories, report deneratione instrument Calibration and Health Phwsics Consulting.
Dr. McGee' Joined RMC in September 1974 as Managerr General Health Phwsics.
He was responsible for Health Physicsr Consulting and Whole Bodw Counting from 1977-78.
During thic Period he developed RMC's first Uranium Lung Counter, calibrated nuclear P13nt radiJtion monitoring swstemst conducted Health Phwsics ALARA desicn review for nuclear facilities, prepared nuclear ~ Plant radiochemistru and nuclear counting procedures and supervised several small decontamination Projects.
He also PreParod rOdiolusiC41 sections-of PSARis, FSARise and ERis.
He was Radiological Site Manager for the U.S.
Armw's Weldon Springs Alternatives Assessment Project.
Dr. McGee received a B.S.
degree in Chemistrv and Phwsics from East Texas Universitw.
He has received a H.S.'in Analvtical Chemistrv and a Ph.D. in Dionucleonics and Environmental Health from Purdue Universitw. -From 1965-67, Dr. McGee was an Environmental Health Fellowe Purdue Universitw.
From 1967-747 Dr. McGee served as Assistant Professor to Associate Professor of Radiochemistrv at Temple Universitw.
He was also Chairman of the Department of Pharmaceutical Chemistrup Director of Radiological Health Specialists Training Program, and Chairman of the Health Science and University Radiation Safety Committees at Temple.
He is the author of several Publicat ns, and is currentlw a member of such Professional organizations as the American Chemical Societw(Analvtical Chemistrw Division) and the Health Physics Societw.
LICENSdh0.
SNM-1524 RR01APR85.NRC (PAGE 9 0F-147).
ATTACHMENT.42(Cont'd)
(Page-4 0F 22)
CHARLES E. NC GEE, PH.D.
TRAIhiNG AND EXPERIENCE-TRAINING:
WHERE DURATION OF On the Job Formal Course TRAINED TRAINING (Yes or No)
(Yes or No)
(a) Principles Purdue U.
2 wears No Yes and Practices Temple U.
7 wears Yes Yes of Radiation (As Lecturer)
~Irotection.
RMC 10 wears Yes No (b) Radioactivits Purdue U.
2 wears-No~
Yes measurements, Temple U.
7 wears Yes Yes stan'dardizations (As Lecturer)
.and monitoring.
RMC 10 wears Yes No techniaues and instruments.
(c) Mathematics Purdue U.-
2 vears
.th)
Yes and calculations Temple U.
7 wears Yes Yes basic to the use (As Lecturer) and measurement RMC 10 uears Yes No of radioactivitv.
(d) Biological Temple U.
7 wears Yes Yes effects of (As Lecturer)
Radiation.
RMC 10 wears Yes No
LICENd bO. SNM-1524 RR01APR85.NRC (PAGE 10 0F 147)
ATTACHMENT 12(Cont'd)
(Page 5 0F 22)
CHARLES E. MCGEE, PH.D.
TRAINING.AND EXPERIENCE (Cont'd)
EXPERIENCE:
Maximum Where the Duration TwPe (Isotopes Quantities Experience of of Handled)
Handled Was Gained Experie.1ce -Use H-3 500 uCi Southwestern 2 wears Research Med. School 10 mci Purdue U.
2 wears Research & Trainins 10 mci
' Temple U.
7 ueers Research 8 Training 10 uCi RMC 10 wears Instr. Calibration 8 Sample Analusis C-14 50 uCi Southwestern 2 wears Research Med. School 1 mci.
Purdue U.
2 wears Research 8 Trainins 50 uCi Temple U.
7 uears Research & Training 50 uCi RMC 10 wears Instr. Calibration 1 Sample Ansivsis Na-22 0.5 mci Purdue U.
2 wears Research & Trainins 0.5 mci Temple U.
7 vears Resecrch 8 Training P-32 50 uCi Southwestern 2 voars Research Med. School 1 mci Purdue U.
2 wears Research & Training S-35 1 mci Southwestern 2 vears Pesearch Med. School Temple U.
7 wears Research & Training Mn-54 0.2 mci Temple U.
7 uears Research 8 Train'ing 50 uCi RMC 10 wears Instr. Calibration
& Sample Analusis Co-60 300 Ci Temple U.
3 uears H.P.
Monitoring 2 mci Temple U.
2 vears Instr. Calibration 10 mci RMC 10 vears Instr. Calibration
& Sample Analvsis Ni-63
'l mci Temple U.
6 months Research 1 Trainins 50 uCi RMC 10 wears Instr. Calibration 2 ~ Sample Analvsis 2n-65 1 mci Temple U.
4 wears Research 8 Trainins 50 uCi RMC 10 wears Instr. Calibration
& Sample Analusis Se-75 1 mci Temple U.
4 wears Research & Trainins Kr-85 10 mci Temple U.
6 months Research & Training 100 mci RMC 3 years Instr. Calibration j
Tc-99m 10 mci Temple U.
1 wear Research & Training l
10 mci RMC 6 months Sample Analvsis As-110m 1 mci Temple U.
2 wearc Research & Training Sb-124 0.5 mci Temple U.
4 wears' Research 8 Training I-125 10 mci Templc U.
4 months Immunoassaw 1 mci RMC 3 uears H.P.
Monitorins 03626 L
LICENSd D. SNM-1524 RR01APR85.NRC (PAGE 11 0F 147)
ATTACHMENT 82(Cont'd)
(Page 6 0F 22)
CHARLES E.-MCGEE, PH.D.
TRAINING AND EXPERIENCE (Cont'd)
' EXPERIENCE!
Maximum Uhere the Duraticn Twee (Isotopes-Quantities Experience of of Handled)
Handled Uas Gained Experience Use I-129 20.uCi Temele U.
2 vears Research & Training I-131 100 mci Purdue U.
6 months Research & Training 500 mci Temple U.
7 vears H.P.
Monitoring 1 mci RMC 5 wears Instr. Calibration-8 Sample Analvsis Xe-133 150 mci RMC 3 wears Instr. Calibration Cs-134 5 mci Templc U.
4 vears Research 8 Training Cs-136 1 mci Temple U.
2 uears Research 8 Training Cs-137 2.2 Ci Purdue U.
1 month Instr. Calibration Cs-137 130.Ci RMC 10 voars
-Instr. Calibration 50 uCi RMC 5 wears Instr. Calibration 8 Sample Analusis Ce-144 10 mci Temple U.
4 wears Research & Trainins Tb-160 1 mci Temple U.
4 wears Research & Trainins Ho-166m 1 uCi Temple Ue 4 uears Research & Training Ta-182 2 mci Temple U.
4 wears Research & Training W-185 5 mci Temple U.
4 wears Research & Training T1-204 2 mci Temple U.
5 wears
.Research & Training Pu-Be (5 Ci-Purdue U.
4 months N. Act & H.P.
exP.
neutron Tempic U.
5 wears Research & Training source)*
Swimming Purdue U.
1 das H.P. Experience Pool Reactor Ra-Be (4.5 mci RMC 3 wears Moisture /Densitw neutron Measurements sotorce)
Al-28,29
- Submicrocurie amounts of manw Activation Products Cl-36 50 uCi Purdue U.
1 time N-40 or less Temple U.
Experiments Fe-59 to manw Research & Training Co-58 experiments Cu-64 over several Sr-90 wears Mo-99 In-116 Sm-151 MFP uCi or RMC 10 vears Instr. Calibration and less
& Sample Analysis various down to individual PCi Per i
isotopes sample.
1 l
LICENd bO. SNH-1524 RR01APR85.NRC (PAGE 12 0F 147)
ATTACHMENT #2(Cont'd)
(Pase 7 0F 22)
RuuER E.
LINNEMaNN, M.D.
PRESIDENT RADIATION MANAGEMENT CORPORATION i;EDICAL SERIVCES DIVISION Dr. Linnemann oversees the operation of RMC Medical Services.
He has direct contact and is responsible for off-site training cnd marketing.
Dr. Linnemann is certified bw the American Board of Radiolosw cnd the American Board of Nuclear Medicine.
He is licensed to practice medicine and surserv in the states of Pennsw1vania, Minnesota and Illinois.
He holds active membership with the American Medical Association, the Societw of Nuclear Medicine, and American Co11ese of Nuclear Phwsicians, and the Radiological Societs of North America.
He serves on menu committees related to radiation medicine, has authored manu Papers which have been published in Professional and technical Journals here and abroad.
He has represented the State of Ponnsw1vania in the Medical Liaison Officer's Network (MLON) since 1971.
He has also been called on bw nuclear utilitu CCDPanies to testifw in their behalf, as an expert witness, in innumerable instances.
He is a native of Minnesota and a 1956 scaduate of the Universitu of Minnesota School of Medicine.
He completed and Internship and Residenew in Radiolosv at the Walter Reed Armw Hospital, Washinston, D.C.
While there, he served as Research Associate in the Department of Radiobioloss at Walter Reed Institute of Resecrch where he inves-tisated the use of anti-radiation drugs in the treatment of concer.
From 1965-68 Dr. Linnemann headed the U.S.
Armv Medical Research Detachment in Europe where he was the radiological health consultant to the U.S.
Arms in Europe and was responsible for plans, procedures, and trainins necessarv for militars hospitals in the evaluation, treatment, and evacuation of radiation casualties.
He also served as the U.S.
Delegate to a NATO Panel of experts on Medical ADP9Ct5 of Nuclear War.
Dr. Linnemann is Associate Professor of Clinical Radiolosv at the Universitw of Pennsulvania School of Medicine and Visiting Associate Professor of Clinical Radiolosv at Northwestern Universitw School of Medicine, Chicaso, Illinois.
0********************t*************************************************
hk)
LICENSdlh0.SNH-1524 RRO1APR85.NRC
-(PAGE 13 0F 147)'
ATTACHMENT *2(Cont'd)
(Pace 8 0F 22)'
ROGER E. LINNEMANN, M.D.
TRAINING AND EXPERIENCE TRAININGt WHERE DURATION OF On the Job Formal Course TRAINED TRAINING (Yes or No)
(Yes or No)
(a) Principles Walter Reed 4 uears Yes Yes and Practices Armv of Radiation Institute of Protection.
Research
- Board Certified in Radiologw (b) Radioactivits Walter Reed 4 wears Yes Yes standardization,-
Armw and monitoring Institute of technioues and Research &
instruments.
General 4 wears Yes Yes Hospitale U.S.
Arms 4 wears Yes Yes Nuc. Med. Research Detachment (Europe)
(c) Mathematics Walter-Reed 1 wear Yes Yes and calculations General basic to the use HosPitalf and measurement U.S.
Armw 1 wear Yes Yes of radioactivitw.
Nuc. Med. Research Detachment (Europe)
(d) Biological Walter Reed 1 wear Yes Yes
-effects of Armw Radiation.
Institute of
- Board Certified in Radiologw Research &
General 3 wears Yes Yes HosPitalF U.S.'Armw 1 wear Yes Yes Nuc. Med.
Research Detachment (Europe)
RMC 14 wears Yes Yes (Ac Lecturer)
LICENd h0. SNH-1524 RRO1APR85.NRC (PAGE 14 0F 147)
ATTACHNENT 12(Cont'd)
(Pcco 9 0F 22)
ROGER E.
LINNEMANN, M.D.
TRAINING AND EXPERIENCE (Cont'd)
EXPERIENCE:
Maximum Where the Duration Tupe (IsotoPos Quantities Exrerience of of Handled)
Handled Was Gained Experience Use Co-60 5000 Ci Walter Reed i ucar Therapw Res. Institute Noble gases mci Walter Reed 3 years Diagnosis Hospital Halosens mci U.S.
Armw 5 years Research Nuc. Hed.
Research(Eurore)
Ra-226 100 ms U.S.
Armw 5 ucars Research Nuc. Hed.
1 Research(Eurone)
Instr. Calibration
..-.s
LICENSdlh0. SNM-1524 RR01APR85.NRC (PAGE 15 0F 147)
ATTACHMENT #2(Cont'd)
(Page 10 0F 22)
LEROY F.
BOOTH, CHP.
MANAGER RADIATION MANAGEMENT CORPORATION NUCLEAR SERVICES DIVISION (MWRO)
Mr. Booth Joined RMC in Januarv of 1979 as a Senior Health Physicist, and wis appointed Manager, Midwest Resional Office, in June of 1980.
He is responsible for Providing health Phv5ics consulting assistance to c'11ents.
Specific responsibilities have been in RMC's Whole Bodv Counter design, development and operation Programs, Emergenew Assistance Program, radio-analvtical measurement Prosram, and remedial action Programs.
Mr. Booth received his B.S.
degree in Chemistre from Northern Illinois Universitu in 1964, and has performed graduate studies in Nuclear Science and Engineering at Catholic Universitv.
Prior to his Position at RMC, he was responsible for imPlementins and directing the contract health physics Program at Goddard Space Flisht Center.
Prior to GSFCr Mr. Booth was a Staff Health Phwsicist at NUSP ProVidins Consulting services in areas such as procedure Preparation, trainins materials PreParationt Program reviews, instrumentation evaluations and waste disposal for nuclear Power Plant clients.
He was a Senior Health Phwsicist for 10 voars at the U.S.
Naval Research Laborators and was responsible for Performins radionuclide analuses and TLD research.
He alro has e::Perience as a Phusical Science Assistant in Radiological Safety Department at the Armed Forces Radiobioloss Research Institute.
Mr. Booth is a member of the American Nuclear Society and the American Health Phwsics Societv(Midwest and Baltimore-Washington Chapters).
He was certified bv the American Board of Health Phwsics in 1972, and is currentiv servins as a member of the ABHP Panel of Examiners.
Mr. Booth has authored or co-authored numerous articles, Papers and technical reports on various health Physics related topics.
LICENd NO. SNM-1524
~'
RRO1APR85.NRC (PAGE 16 0F 147)
ATTACHMENT #2(Cont'd)
(Pcde 11 0F 22)
LEROY F.
BOOTH, CHP.
TRAINING AND EXPERIENCE TRAINING:
WHERE DURATION OF On the Job Formal Course TRAINED TRAINING (Yes or No)
(Yes or No)
(a) Princirles AFRRI 2 voars Yes Yes and Practices NRL 10 vears Yes No of Radiation NUS 1 vear Yes No Protection.
RMC 6 vears Yes No (b) Radioactivity AFRRI 2 vears Yes No teasurements, NRL 10 vears Yes No standardi stion, NUS I wear Yes No cnd monitoring Catholic U.
0.5 vear No Yes technioues and RMC 6 voars Yes No instruments.
(c) Mathematics AFRRI 2 wears Yes No cnd calculations NRL 10 uears Yes No basic to the use NUS 1 vear Yes No and measurement Catholic U.
0.5 vear No Yes of radioactivitw.
RMC 4 vears Yes No (d) Biological AFRRI 2 wears Yes No offects of NRL 10 wears Yes No Radiation.
RMC 6 vears Yes No
()
LICENSh0.
SNM-1524 RR01APRE.NRC (PAGE 17 0F 147)
ATTACHMENT f2(Cont'd)
(Pase-12 0F-22)
LEROY F.
BOOTH, CHP.
TRAINING AND EXPERIENCE (Cont'd)
EXPERIENCE!
Maximum Where the Duration TwPe (IsotoPos Quantities Experience of of Handled)
-Handled Was Gained Experience Use H-3 5 Ci AFRRI & NRL 3 wears Accelerator, Targets Mn-54 1 mci NRL 10 wears Instr. Calibration Co-60 200 Ci NRL 5 wears Instr. Calibration Zn-65 1 mci NRL '
10 wears Instr. Calibration Ba-133 100 uCi NRL-10 wears Instr. Calibration Cs-137 30 Ci NRL 5 uears Instr. Calibration Ra-226 10 ms NRL 10 wears Instr. Calibration
-Am-241/Be
'10 Ci NRL 8 uears Dosimetrw Cf-252 1 ms NRL 4 wears Dosimettw MFP uCi or NRL 10 wears Instr. Calibration and less
& Sample Analvsis various down to individual PCi Per isotopes sample.
0 LICENw.sNO. SNM-1524 RRO1APR85.NRC (PAGE 18 0F 147)
ATTACHMENT *2(Cont'd)
(Pace 13 0F 22)
FRAZIER~L. BRONSON, M.S.,
CHP.
VICE PRESIDENT
. RADIATION MANAGEMENT CORPORATION NUCLEAR SERVICES DIVISION As Vice President of Nuclear Services, Mr. Bronson is responsible for overseeing all whole bods counting services and technical development for the Nuclear Services Divsion.
l
'In 1975 Mr. Bronson was named General Manager of RMC's Midwest l
Office in Northbrook, Illinois, where his responsibilities included develoPins definitive marketing programs for. nuclear rower Plantst hospitals, universities, and similar institutions) coordinatins
~
training / exercise Programs for supporting hospitals and Plant Personnell establishing a Radiation Emersenew Medicine (REM) Team
' including accident response, communicctions, transPortationF and trainins of RMC Personnell and Performind technical consultation services to the nuclear industrw.
i Mr. Bronson Joined RMC in 1969 as Director of Radiological Phwsics.
He was responsible for the operation and management of RMC's radioanalvtical laboratories.
Durins th2s Period he designeda constructed and calibrated the following instruments /
sustems' Mobile Whole Bodw Counter) Computer-Based Multiple Pulse Height Analwzer with alphar beta and damma scintillation and solid state detectors) Beta-Gamma Coincidence Counter for low level measurement of I-131) Thermoluminescent Dosimetru Swsteal Gamma Calibration and Exposure Facilitvl Automatic A1Pha and Beta-Counting Swstemsi and Air Flow Calibration Facilitv.
He is a consultant to the nuclear utilitw industru in the areas of general health Phwsics, air and liould sampling techniouDsr Personnel dosimetrue effluent measurement sustems, environmental monitoring methodolosv, Por. table and laboratorv instrumentation, and measure-ment and dose assessment of accidental overexrosures to external or airborne radiocontaminants.
Mr. Bronson received a B.S.
degree in Nuclear Engineerins from the University of Missouri School of Mines and Metallursw and a M.S.
dedree in Radiological Healtn from the Universitw of Oklahoma.
Mr. Bronson is a member of the American Board of Health Phwsics l
Certification Panel, National Health Phwsics Societw, Delaware Vallew Chapter of the Health Phusics Societw(Secreterv/ Treasurer and President)-and the American Nuclear Societs.
i a-
g LICENSdlh0. SNM-1524 RR01APR85.NRC (PAGE 19 0F 147)
ATTACHMENT #2(Cont'd)
(Page 14 0F 22)
FRAZIER L.
- BRONSON, M.S.,
CHP.
TRAINING AND EXPERIENCE TRAINING'-
WHERE DURATION OF On the Job Formal Course TRAINED TRAINING (Yes or No)
(Yes or No)
(a) Principles U.
of 2 scars No Yes and Practices Missouri of Radiation U.
of 1 vear No Yes Protection.
Oklahoma AFRRI 3.5 vears Yes Yes c.
RMC 16 wears Yes Yes (As Lecturer)
(b) Radioactivitu U.
of 2 uears No Yes ceasurementse Missouri standardization, U.
of 1 wear No Yes and monitoring Ok1choma technioues and AFRRI 3.5 vears Yes Yes instruments.
RMC 16 vears Yes Yes (As Lecturer)
-(c) Mathematics U.
of 2 uears No Yes and calculations Missouri basic to the use U.
of 1 wear No Yes and measurement Oklahoma AFRRI 3.5 vears Yes Yes of radioactivitv.
RMC 16 uears Yes
.Yes (As Lecturer)
(d) Biological U.
of 2 usars No Yes effects of Missouri Radiation.
U.
of 1 wear No Yes Oklahoma AFRRI 3.5 wears Yes Yes RMC 16 vears Yes Yes (As Lecturer) 0362G
LICENdlhNO. SNM-1524 RR01APR85.NRC (PAGE 20 0F 147)
ATTACHMENT #2(Cont'd)
(Pede 15 0F 22)
FRAZIER L.
- BRONSON, H.S.,
CHP.
TRAINING AND EXPERIENCE (Cont'd)
EXPERIENCE Maximum Where the Duration TVPe (Isotopes Guantities Experience of of Handled)
Handled Was Gained Experience Use
- tt****
Co-60 10 mci RMC 10 wears Instr. Calibration Cs-137 120 Ci AFRRI 3.5 uears Instr. Calibration 130 Ci RMC 10 vears Instr. Calibration MFP uCi rande AFRRI 3.5 wears Research & Training and or less U.
of 1 vear Training various down to Oklahoma individual PCi per RMC 10 vears Inctr. Calibration isotopes
- sample,
& Sample AnalHsis
- t***********************************
[
LICEP"]85.NRC NO. SNM-1524 O
RR01(_j (PAGE 21 0F 147)'
ATTACHMENT #2(Cont'd)
(Page 16 0F 22) t JOHN P.
ANDREWS SENIOR HEALTH PHYSICIST RADIATION MANAGEMENT. CORPORATION NUCLEAR SERVICES DIVISION (NERO)
~Mr.
Andrews Joined RMC in March of 1981 3s a Senior Health Phwsicist.
Mr. Andrews has been active 19 engaged in RMC training
-activities includins advanced level training in calibration of radiation monitoring instrumentation for NBS and development of other training Programs including a Course assessment of the Internal Dosimetrv Course.
He has also developed computer codes for off-site dose assessment as reuuired bw Res. Guide 1.21 and made assessments of environmental doses from releases of radionuclides.
Currentlu, he is PreParins a man'J31 for the implementation of an off-site computer Program.
Mr. Andrews also has current responsibilitw for the 130 Curie Cs-137 irradiation
. source.
In this CaPacitu he oversees calibration of radiation surves meters and oualitw assurance for TLD dosins.
Mr. Andrews is an auditor and licensins consultant for several major clients.
Before Joining RMC, Mr. Andrews was Surervisor of Health Phwsics and Radiation Safetw Officer for Cata19 tic, Inc., for six wears.
In this capacity he was responsible for the corporate radiation Protection Program and for the licensing and radiation safetw aspects of the Catalvtic radiograPhw Program.
He Provided radiation Protection audit oversight for maintenance activities at nuclear Power Plants.
This included review and audit of site radiation Protection Procedures for Catalvtic workmen and suP9Pvision of Catalvtic field health Ph'Jsics coordinators and technicians.
Mr. Andrews provided ALARA ensincerins review for all nuclear engineering Projects.
Mr. Andrews was a Senior Health Phwsicist for NUS and Corporate Health Physicist for SUNTAC Nuclear Corporation for three wears.
While with SUNTAC, he Prepared the radiation Protection docuPentation for Peach Bottom Unit i decommission ~ ins and the General Atomic ComPans, End-of-Life Primarv coolant sustem samplins Program, for that facilitv.
He was also operations 119 responsible for radiation Protection activities during the clean-up of a severelv contaminated-rad waste facilitw and for the repair of damaged downcomers at Indian Point-in 1973.
Mr. Andrews was Health Phwsics Operations Supervisor for Gulf General Atomic in San Diego.
During that tenure, he was responsible for all technician services, radiation monitoring eouiPment, and emergenew response capabilitv.
In addtion, he established and implemented the environmental and bicassaw Programs and managed the Health Phusics Laborators at that facilitw.
He also established a Program for determining enriched uranium MUF(material unaccounted for) and in-duct work in the Presence of thorium in the feul development and fabrication Program for the HTGR reactors.
Mr. Andrews holds a degree in math from San Diego College and has completed a variety of suPPlementarv courses in statistics, computer Programmins, and nuclear radiation monitoring.
He is also a member of the American Nuclear Societs and ASTM, and ParticiPatos in the E10.03 committee activities for that organization.
He has been active with the AIF'and NESP in the In-Processind area.
He is a member of the Delaware Vallew Societw of Radiation Safetw.
()
LICEN()NO.
SNM-1524 RR01APR85.NRC (PAGE 22 0F 147)
ATTACHMENT *2(Cont'd)
(Page 17 0F 22)
JAMES D. GIBSONr-NBA, CHCM.
MANAGER RADIATION MANAGEMENT CORPORATION NUCLEAR SERVICES DIVISION (NERO)
- 7**********************************************
Mr. Gibson has over 14 wears of experience in Providins radiation Protection services and supervising health Phusicists.
In' August 1983, Mr. Gibson Joined RMC as Manaser of the Nuclear Services Division Northeast Resional Office.
In this capacitw he is responsible for strategic Planninst marketing, ProPos31 Preparation / daw-to-daw operations of the regional office and functions as Project manager for large scale. operations.
Durins the Period of March 1982 to Julu 1983, Mr. Gibson was emPloved 69 Associated Technologies Inc. as manager of their Hea'Ith Phwsics Services Division.
During his enPlowment with ATI, he established the divisione developed and implemented marketing and operating Programs and guided the division through its start-up Phase.
While at ATI, Mr. Gibson was involved in several Projects including!
the development and administration of an Emergencu Response Training Prosrom for Arkansas Power and Licht Co.,
a Job task analwsis for reactor operators at PSE8G's Salen Nuclear Power Station and an instructional swstems desian format General Emplovee Trainins Program for Yankee Atomic's Rowe Nuclear Power Station.
Prior to Joining ATIr Mr. Gibson was emPlowed bw the Stone and Webster Engineering Corporation for eight wears as the Corporate Radiation Safetw Officer (RS0).
Durins this Period he was responsible for managins the Corporate Office of Radiation Safetw and the formulation, implementation and enforcement of a corporate radiological safetw Program for over 5,000 emPlowees.
During his tenure as RSO, Mr. Gibson comPletelv reorganized and revitalized Stone 3nd Webster Engineerins Corporation's corporate radiological safatu Program.
Amons his incorporations WereI Computerized Radiation EMPosure Management Swstem (CREMS), TLD system for Personnel dose monitoring, Nuclear Support Services Program for reactor outades, radiodraPhw operating and emergenCv Procedurest MicrocomPuterized ALARA Control Swstem (MACS) and several radiation safetw training programs.
Prior to Joining Stone and Webster in 1974, Mr. Gibson was the Radiation Safetw Officer for all NRC licensed activities Performed at the Newport News Shipbuilding ComPanw.
During his four weces at Newport News, he developed new oPeratins and emergenCw Procedures, trainind Programs, source accountabilitw/ leak. testing /cclibration and recordkeeping Procedures and comPletelu reorganized the companw's r
Radiological Safets Auditing Program.
f Mr. Gibson holds a B.S.
degree in Biolodw from The Virginia Hilitarv Institute and a MBA. form Northeastern Universitw.
He is a Certified Hazard Control Manager (Master Level), and a member of the American Nuclear Societv, the American Health Phwsics Society and American Societw of Non-destructive Testing.
A (m)
LICEN(m,NO. SNM-1524 RR01APR85.NRC (PAGE 23 OF 147)
ATTACHNENT #2(Cont'd)
(Pase 18 0F 22)
LARRY F.
UMBAUGH SENIOR RADI0 CHEMIST RADIATION MANAGEMENT CORPORATION NUCLEAR SERVICES DIVISION (NERO)
Mr. Umbaugh recent19 Joined RMC as a Senior Radiochemist.
He Possesses over 17 vears of technical experience in the nuclear industrv Principal 19 in the areas of radiochemistrv, radiation Protections and instrumentation and controls.
Before Joinins RMC, Mr. Umbaugh was Chemistrv/ Instrumentation Foreman for GPU Nuclear Corp. at the Three Mile Island Nuclear Station-Unit-1 for 2 vears.
In this caPacitu he was responsible for the daw to das operation of the chemistrv and countins labs including evaluating new eauiPmentr writins Purchase specifications, evaluating bids, Placing orders, overseeins eauiPaent installation and calibration, Procedure writing, and training on new instrumentation.
A principal resronsibilitw was functioning as the Project manager for the installation of a larse Computer based samma sPectroscoPv/chemistrw
~
sustem.
He was'also the swstem-manager for this swstem, with resPonsibilitw to develop and maintain the computer software and train other supervisors and technicians on the use of the swstem.
Prior to Joining GPU Nuclear Corporation at THIr Mr. Umbaugh was a Radiochemistrv/Chemistrv Foreman for River Bend Nuclear Station Unit-1 for 2 vears.
While with Gulf States (GSU), Mr. Umbaugh designed chemistrv and radiochemistrv labs, prepared lab slassware and chemical Purchase orders, Prepared chemistrv 13b and Counting room eouiPhent specifications, developed and maintained chemistrv lab and counting room software and developed and conducted an'inhouse Chemistre Technician Training Program.
As a member of the Facilitw Review Committeer he Provided Primarv input to Project Licensing on those Portions of the Plant technical specifications Pertaining to the chemistrv Program.
He was responsible for evaluation of samPlins needs for Post-accident samplins, routing of sample lines, evaluation and selection ~of the Post-Accident Sampling SVstem(PASS), samPlins Panel and interfacing with the Architech/Ensineer.
Mr. Umbaugh also developed a Suppression Pool Cleanup Plan that saved GSU between
$3 and $5 million.
Before his affiliation with GSU, Mr. Umbaush was the Senior Nuclear Technician / Technical Assistant for Salem Nuclear Generating Station.
During this 5 wear Period, he analszed and evaluated chemistrv and radiation datal assembled data and Prepared rePortsI determined reouirements for routine and non-routine radiation Protection measures; maintained and adjusted Process chemical eauipmentf inspected, adjusted, rcPairedP and inst 3lled Power FICnt instruments used for samplinst detection, measurement and analvsisl inspected internal surfaces of steam seneratorst condensers, heat exchangers, etc.) Performed chemical and radiation tests to develop radiation safetw/chemistre Procedures and methods) and supervised training of lower classification Personnel and contract Radiation Protection Chemistrv technicians.
He was also involved in Pre-startuP testinst start-uP, Power testinst commercial operation and refueling L
{
of Salem Unit 2.
1.
- D)
D
(_
LICEN%,NO. SNM-1524
.RR01APR85.NRC (PAGE 24 0F 147)
ATTACHMENT #2(Cont'd)
(Page 19 0F 22.4 LARRY.F. UMBAUGH (Pase 2)
' SENIOR RADI0 CHEMIST Previous to his emPlowment with Salem, Mr. Umbaugh was a Nuclear Fuel Chemistry Tech Process Control technician for Westinghouse Plutonium Fuel Development Lab. and Babcock I WilCoX Plutonium Lab for 8 wears.
He was responsible for Chemical and
' radiochemistry analvsis oni incoming raw Plutonium and uraniump final' Product (reactor fuel), reactor test loops and associated Components and all outgoing waste.
He was also resronsible for sPecial nuclear material accountabilitw and control which involved:
controir' inspections samPlind and aCCountabilitW of fuel from receipt of raw materials through melting, castinds millins, incaPsulation and shipping for the FFTF and ZPPR projects.
t I
t
j LICENdlhNO. SNM-1524 RRO1APR85.NRC (PAGE 25 0F 147)
ATTACHMENT 12(Cont'd)
(Pace 20 OF 22)
WAYNE D.
V0 GEL, B.A.
HEALTH PHYSICIST RADIATION MANAGEMENT CORPORATION NUCLEAR SERVICES DIVISION (NERO)
Mr. Vosel is responsible for the operation, Coordination, training and technical developments related to various health Physics seevices especial 19 Whole Bodw Counting and Respirator Fit Testing.
Mr. Vogel has extensive experience in all activities of the Nuclear Services Division, including Instrument Calibration and Repair, Field Survewing, Bioassaw, Environmental Monitorins, Internal / External Dose Calculations, Microcomputers and Computer Programmins.
His expertise lies in the areas of electronics, use and safe handlins of radionuclides, x-rav diffraction, H.P.
consulting and Uranium Lung Counting.
He is also experienced in the fields of radiation and radioactivitw measurements, field survevs and has instrumentation experience in Multichannel ana19:ers, TLD eaviement, Microcomputers and Electronics Test eauipment.
Since Joinins RMC as a Technicain in 1976, Mr. Vogel has held Positions of Whole Bod 9 Countind Supervisor, Counting Laboratorv Supervisor and Whole Body Counting Manager.
His responsibilities in these Positions included training, coordination and technical development related to Whole Bodw Counting in the Northeast Regional Office.
Mr. Vogel ic draduate of Temple Universitw where he received a B.A.
degree in Phusics in 1974.
In 1976 he attended Drexel University Graduate School where he was a Hechanical Engineer student.
He is a Plenary member of the Health Phusics Societs and the National Honor Societs.
(~'T n
U LICEN O NO. SNM-1524 RR01APR85.NRC (PAGE 26 OF 147)
ATTACNMENT 42(Cont'd)
(Pase 21 0F 22)
WAYNE D. V0 GEL TRAINING AND EXPERIENCE TRAINING:
WHERE DURATION OF On the Job Formal Course TRAINED TRAINING (Yes or No)
(Yen or No)
(a) Principles RMC 8 wears Yes No and Practices of Radiation Protection.
(b) Radioactivitw TEMPLE U.
i wear No Yes ceasurements, RMC 8 vears Yes No standardization, and monitoring techniaues and instruments.
(c) _ Mathematics Temple U.
1 wear No Yes and calculations RMC 8 wears Yes No basic to the use end measurement of radioactivitv.
(d) Biological RMC 8 wears Yes No offects of Radiation.
N
,4
LICEN$NO.
SNH-1524 RR01APN05.NRC (PAGE 27 0F 147)
ATTACHMENT *2(Cont'd)
(Parte 22 0F 22)
WAYNE D.
V0 GEL TRAINING AND EXPERIENCE (Cont'd)
EXPERIENCE:
Haximum Where the Duration TVPe (Isotopes Quantities ExPerjence of of Handled)
Handled Was Gained Experience Use Co-60 10 mci RNC 5 wears Instr. Calibration Cs-137 130 Ci RMC 3 vears Instr. Calibration I-131 0.1 mci RMC 5 vears Instr. Calibration U-235 38 nCi RMC 2 vears Instr. Calibration NFP 50 uCi RMC 5 wears Instr. Calibration cod or less 1 Sample Analusis various down to individual PCi per isotopes sample.
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ClR25JgN,85,JiRC
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L NSE NO. 37-13129-01 RR25JAN85.NRC (PAGE 62 0F 169)
ATTACHMENT 86(Cont'd)
(Page 13 0F 24)
SUMMARY
OF ITEM 9:
(Cont'd)
FACILITIES AND EQUIPMENT:
B.
EauiPmentI USE ADDRESS 3A.(3508 AND 3440 MARKET ST)
TYPE OF MANUFACTURER'S-MODEL NUMBER RADIATION SENSITIVITY i
~ INSTRUMENT NAME NUMBER AVAILABLE DETECTED RANGE SURVEY EQUIPMENT:
Portable Eberline RM-14 3
Alpha /
20.to Radiation Beta /
50,000 cem Monitor S/N 1729r. 3141, 4000 Gamma Portable Eberline PIC-6A 1
Ion Chamber S/N 2076 Geiger Eberline E-400 1
AIPha/
Counter S/N 3781 Beta /
f Gamma Teletector Eberline 6112 1
Gamma f
S/N 55451 Sample Eberline SH-4A 1
NA NA
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Changer Portable Ludlum 177 1
Radiation S/N 31881 Monitor i
Count Ludlum 2220 1
l Rate S/N 31974 l
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Changer S/N PR016039 I
l Portable Johnson 1
Alpha /
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(
Gamma Dosimeters:
Various Various 3
Gamma 0-20 R 1
Gamma 0-5 R
1 Gamma 0-1 R
t 16 Gamma 0-200 mR l
LI 1SE NO. 37-13129-01 RR25JAN85.NRC (PAGE 63 0F 169)
ATTACHMENT #6(Cont'd)
(Pace 14 0F 24)
SUMMARY
OF ITEM 9i (Cont'd)
FACILITIES AND EQUIPMENT:
B.
Eauipment:
USE ADDRESS 3A.(3508 AND 3440 MARKET ST)
TYPE OF MANUFACTURER'S.
MODEL NUMBER RADIATION SENSITIVITY INSTRUMENT NAME NUMBER AVAILABLE DETECTED RANGE
- f**'
' I Dosimeter Chargers:
Johnson CAT 6 2
NA NA S/N 2369, 2422
'Landsverk L-136 1
NA NA Miscellaneous
. Supplies:
10 mrem Gamma 500 Rem Per
(
Ouarter TLD Ring Landauer 10 Beta /
20' mrem
(
Gamma 500 Rem Per Guarter e.
i Air Eberline 1
NA NA Sampler S/N 0777
-m y
Air StaPlex TF1A 1
NA NA Sampler S/N 5108 Respirators ~MSA Comfor 7
NA NA II Filter MSA TVPe
'H' 10 NA NA Cartridges Comfo II TVPe 6
NA NA GHI-H 4
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I
Li 1SE NO. 37-13129-01 RR25JAN85.NRC-(PAGE 64 0F 169)
ATTACHMENT 86(Cont'd)
(Page 15 0F 24)
SUMMARY
OF ITEM 9:
'(Cont'd)
FACILITIES AND EQUIPMENT:
B.
Eauipment:
USE ADDRESS 3A.(3508 AND 3440 MARKET ST)
TYPE OF MANUFACTURER'S MODEL NUMBER RADIATION SENSITIV(TY INSTRUMENT NAME NUMBER AVAILABLE DETECTED RANGE COUNTING LABORATORY INSTRUMENTS:
LIQUID SEARLE MARK II 1
Alpha /
0 to SCINTILLATION ANALYTIC Beta /
1 million
~~
COUNTER Gamma cem
-- with 300 sample capacitw automatic sample Chandere PROPORTIONAL CANBERRA 2404 1
Alpha /
0 to COUNTER Beta /
100,000
-- with 50 sample capacity Gamma cpm 4
automatic sample changer.
GAMMA CANBERRA Series 90 1
Gamma O to SPECTROSCOP)
MCA 1 million i
SYSTEM --
cpm with 20% IG
- detector, (with shield) and PDP 11/23 Plus Computer based automatic damma analvsis with APOGEE software and associated electronics.
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LICENSE NO. 37-13129-01 RR25J^*:85.NRC
(_)
(PAG ( )5 0F 169) f
'~3 14 )
ATTACHMENT *6(Cont'd)
(Pace 16 0F 25)
SUMMARY
OF~ ITEM 9:
(Cont'd)
FACILITIES AND EQUIPMENT.
B.
Eauipment:
USE ADDRESS 3B.(3356 COMMERCIAL AVENUE)
TYPE OF MANUFACTURER'S MODEL NUMBER RADIATION SENSITIVITY ~
INSTRUMENT NAME NUMBER AVAILABLE DETFCTED RANGE SURVEY INSTRUMENTS:'
Portable Eberline RM-14 1
Alpha /
50 to Radiation S/N 491 Beta /
50,000 cpm Monitor Gamma Alpha Eberline PAC-4S 1
Alpha Counter S/N 3263 w/AC3 Probe
' Panoramic' Victoreen 470 1
Ionization Chamber Portable Johnson PCS-1 1
A1Pha/
Counting Beta /
Swstem Gamma Consisting of
-Model GSM-5 Surves Meter Alpha / Beta SP-2A scintillation Probe GSP-2A Gamma scintillation Probe GP-90 Beta / Gamma deiger Probe GP-200 alpha / beta /$ammD deiger Probe GP-200x50 alpha / beta /samma deiger Probe ASA-2 speaker DIG-1 scaler MSC-1. sample / Probe mount
-VP-2E variPulscr teGt Pulse generator Dosimeters:
Various Various 8
Gamma 0-200 mR Dcsimeter
~
Chargers:
Johnson CAT 6 1
NA NA t*******
S/N 939 e
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LICEI)NO.
37-13129-01 RR25JAN85.NRC (PAGE 66 0F 169)
ATTACHMENT $6(Cont'd) 44
- N2 (Page 17 OF 24)
SUMMARY
0F ITEM 9:
(Cont'd)
FACILITIES AND EQUIPMENT:
B.
Eouipment:
USE ADDRESS 3B.(3356 COMMERCIAL AVENUE)
TYPE OF' MANUFACTURER'S MODEL' NUMBER RADIATION SENSITIVITY INSTRUMENT NAME NUMBER AVAILABLE DFTECTED RANGE Miscellaneous Supplies TLD Badge Landauer 10 Beta /
10 mrem Gamma 500 Rem Per Guarter TLD Ring Landauer 10 Beta /
20 mrem Gamma 500 Rem rer Ouarter j
Respirators MSA Comfo II 3
NA NA Filter Comfo II GMA-H 4
NA NA Cartriddes COUNTING LABORATORY INSTRUMENTS:
PROPORTIONAL GAMMA 1
A1Pha/
COUNTER PRODUCTS Beta u/ automatic sample channer.
l GAMMA CANBERRA 1
Gamma SPECTROSCOPY SYSTEM with IG detector (with shield), Series 35 HCA.
and associated electronics.
USE ADDRESS 3C.(ONE' STATE STREET)
SURVEY INSTRUMENTS:
Portable Victoreen Panoramie.
1 Bets /
Radiation Gamma Monitor NOTE:
Other Radiation Detection Instruments are available (if needed) from Canberra Industriess.Inc. (License No. 06-15099-01) which is located at the same address.
I
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/" 't LIC NO. 37-13129-01 RR25 N85.NRC I
(PAGE 67 0F 169)
ATTACNMENT *6(Cont'd) 3 (Page 18 0F 24)
SUMMARY
OF ITEM 9:
(Cont'd)
/
I FACILITIES AND EQUIPMENT:
B.
EauiPment!
)
USE ADDRESS 3D.(3440 MARKET ST. 1 1455 SCHUYLKILL ROAD (ROUTE 724)
TYPE OF MANUFACTURER'S MODEL NUMBER RADIATION SENSITIVITY I
INSTRUMENT NAME NUMBER AVAILABLE DETECTED RANGE l
Area Nuclear GA-2T 2
Gamma 0.1 to Monitor Chicago 1000 mR/hr
)
Survev Eberline E-120 2
Beta / Gamma 0.1 to Meter 2000 mR/hr
)
Surves Eberline RM-14 2
Beta / Gamma 20 to Meter 50,000 cpm
)
Portable Johnson PCS-1 2
Alpha / Beta 20 to Surves
& Gamma 50,000 cpm Kit Portable Canberra Series 10 1
Gamma NA Gamma
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m 213/245 0107 740 SALEM STRE ET. GLINDALE, C AllF OnNI A S1703
- Counting Systems Nuclear Application-Irradiation Equipment J
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ADDENDUM SERIES 28 CALIBR ATORS
~
WITH PR ESET TIME, FAIL-SAFE SOURCE RETURN OPTION
~
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I. OPER ATION
~
Power cord must be plugged into a 115 volt, 60 Hertz, single phase plug.
External interlock switch connected to the interlock connector on the control box must be closed or the source will not latch in the " expose" position.
j To preset time on timer:
- 1. Depress the reset button to the left of the lower set of digits on the timer and raise the red cover over the upper set of digits by sliding it upward.
I 2.- Rotate'the wheels on the up'per set of digits until the preset time desired is dialed.in.
- 3. Close the red cover.
Raise the source 'to the " fully exposed" position. At this position a spring l
r e tu rn, solgnoid activated latch engages the source rod.
The source may be automatically returned to the " fully shielded" position by any of the following methods:
- 1. Expiration of the preset time.
- 2. Operation of the manual "off switch.
- 3. Interruption of power supply.
and the timer automatically reucts the previous time preset.
(
- 4. Opening of interlock.
J'
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p CENSE No. 37-13129-01 ATTACHMENT #6(Cont'd).
25JAN85.NRC (PAGE 21 0F 24)
AGE 70 0F 167) 1r
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Timer Reset I
- 1. At the end of an exposure, the timer may be reset to the tirne previously
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preset by pushing the black reset button on the timer.
- g
- 2. The timer is automatically reset to the previous preset time by raising
.t.
the source rod SLOWLY to the " ext ose" position.
CAUTION: If the operating rod is raised swiftly to the " expose" position, 4
the timer will not' fully reset and will jam.. It will not be functional and will not return the source to the " fully shielded" position at the end of the preset time. The operator can casily determine the proper lifting rate
~
for the source rod by observing that the set of digits beneath the cica-cover are reset to 0 as the source is being raised..If any of tl.c numbers I
remain, other than 0, under the cicar cover, the timer has not been
[
completely reset ans will jam'.
The proper lifting rate for the source operating rod is approximately one second for full travel to insure that l_
the timer is fully reset.
~
II. SAFETY f
The source is returned to the " fully shielded" position by gravity whenever l
the conc'itions ~ occur as lis ted above.
+
l 4
t i
III. SERVICING I,
l If for 'any reason, the source does not return to the " fully shielded" position, call the manufacturer for servicing instructions.-
4 i
IV. EXTEll'NAL 11 ALIATION LIGHT l--
A 2 pin Amphenol connector is provided and labeled, which provides power i
for an external radiation lamp or buzzer. Power provideci is 115 volt, A. C.
j.-
and the lamp or buzzer connected to the external irraeliate connector should not exceed 3 amps. If power consumption is greater than I amps, a relay l
will be needed to be connected to external light or buzzer of which the coil will be operated by the power from the unit.
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25JAN85.NRC ~
(PAGE 23 OF 24)
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C A'L I B M A T I O N CERTIFICATE R
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Radiation Management Corporation
- 13. 0. 1803-03-12227
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130 Ci.
Cs, J. L.S. A-0009-6 capsule i.ie un 61ng:
Model.28-10 Calibrator with Model 154 Manual Attenuator Syste'm.
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Tlii t. :.>rnig.:n n eu te r I-1:5 calite r a tesl Isy I)<>:[inic t.? c:. I nrte r!-e r. t.I.imt i L:; ca tjle ra tiesii i:s ili r. c tly traccalete les National lin reau ut titandp reh;.
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L 'i s:,i t io n:
' centered in beam: port t
Di:s tance:
- 1. 00 meters from centerline of source
- 98. 9 centimeters from outside-the source tulac
- 75. 3 centimeters.from face of shield
.s so 2.:n t:
38'.1 R /hr D
u isab:: April 4, 197.8 r
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LICENSE NO. 37-13129-01 O.
ATTACHMENT #6(Cont'd) 25JAN85.NRC (PAGE 24 0F 24)
PAGE 73 0F 169) g anelchsocial:1 s
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- , Ls 740 SALEM GTREET. GLENDALE. CAllFORril A 01203 213/7 % 0111 0
Irr:di.~ tion Eriniptucnt Countiin Sy. stem:
?!tr';I,r ApplicatintT CERTIFICA'110N FOR Model 154 Manual Attenuator Customer: Radiation Management -
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LissNSE NO. 37-13129-01 RR25JAN85.NRC (PAGE 74 0F 169)
ATTACHMENT #7 (Page 1 0F 89)
SUMMARY
OF ITEM 10:
RADIATION SAFETY PROGRAM.
The Radiation Safets Program is designed to assure compliance with 10CFR Parts 19 and 20, applicable NRC and state licenses, and RMC's GA Manual where client services are involved.
The GA Manual governs, the PrePar3 tion, distribution and Control of all aualitw related Procedures.
A new QA Manual (CoPw enclosed) was developed after RMC's Purchase bw Canberra Industries.
Other Procedures are continual 19 being reviewed, improved and revised to assure full implementation of the PoliCv Contained in the GA Manual.
A Partial list of current Procedures (copies enclosed) that are-most pertinent to the Radiation Safetw Program follow:
1.
GA Mcnual(Rev. 2), RADIATION MANAGEMENT CORPORATION 3508 MARKET STREET, PHILADELPHIA, PA.
19104.
[See Attachment #7(Page 2-25); PAGE 75-903 2., PROCEDURE No. R-9(REV. 1), RADIATION PROTECTION PROCEDURE.
(
ESee Attachment #7(Page 26-38); PAGE 99-1113
- Will be reviewed / revised 69 the current RSO to assure compliance with the GA Manual and current Federal and I
State regulations.
a 3.
PROCEDURE No. N1, GENERAL USE OF THE Cs'-137 GAMMA CALIBRATOR.
(
ESee Attachment #7(Page 39-45); PAGE 112-1183 4.
PROCEDURE NO. N2(REV. 2), CALIBRATION OF RADIATION SURVEY e
INSTRUMENTS.
[See Attachment 47(Page 46-60); PAGE 119-133]
5.
PROCEDURE NO. H3(REV. 2), REPAIR OF RADIATION GURVEY INSTRUMENTS.
[See Attachment #7(Page 61-66); PAGE 134-1393 6.
PROCEDURE NO. N5, SEALED - SOURCE LEAK TES
T. PROCEDURE
ESee Attachment #7(Page 67-71); PAGE 140-1443 7.
PROCEDURE NO. N12(REV. 0), GENERAL PROCEDURE FOR PERFORMING RADIOLOGICAL SURVEYS.
t CSee Attachment #7(Page 72-89); PAGE 145-1623 l.
.-....>n ATTAC!DIENT #7(Cont'd)
^
CA Manual
'PAGE 75 OR 169)
(Page20F87)
June 1994 Revi s ion 2 83
/42 R ADI A T I ON M AN AGE *4E NT C CRPOR A T I D4 3508 Merket Street P.
O.
Box 7940 DHILADELPHIA, PEN!aSYLVANIA 19101 CORPORATE QUALITY ASSURANCE MANUAL (Pev. 2)
APPROVED BY:
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~
(a kichard I'MbKern5n~~~~~~~~~~~
O$te' T
president and Chief Executive Officer CONCURRENCF:
~
n 9 /f _.,_
_ $_W ^
Sgadr' 4 nemanV M.D.
wat.
P s'
.n t, Medical Services l
=/- - -
s U/h,
5 l'/
Paul L.
Harmon
=
(Date General Manager, Environmental Services C n ellavecchia ate General Manager, Nuc ear-Services Y
Louise R. Ward Date Manager, Qual ity Assuratice Assiqned To:
Controlled Cooy Uncontrolled Cooy t
i 1
u, c..s a n.s u. a i-1.$ 12 9-u t ATTACIDIENT ' # 7 (Con t ' d )
CA "anoa:
(R25JAN85.NRC (Page30FSp PACE 76 0F 169)
June l '; ? %
Pevision ?
Sj
/e/ 7 TABLE OF C Or, rE N T S E:19 2 Ecrisiee INTROJUCTInN UM-1 1
STATEMENT OF POLICY AND AUTHORITY j f :- 3 L
1 0 ORGANIZATION AND RESPONSIBILITIES Q '4 - 5 1
1.1 President / Chief Executive Officer OM-5 1
1.2 President, Medical Services Division OH-5 1
1.3 General Manager, Env i r onme n t al Services Di vision OH-5 1,
1.4 General Manager, Nuclear Services Division 03-6 1
1.5 Manager, Quality Assurance QM-6 1
1.5 1 Cuality Assurance Committee OM-7 1
1.5 2 Divis ion Coordinator, Quality Assurance OM-7 1
1.5.3 Documen t Custodian OM-8 1
2.0 QUALITY ASSURANCE PROGRAM 0.4 - 9 1
21 General 0M-9
'l 22 Scope QM-9 1
2.3 Quality Assurance Manual Control QM-10 1-2.4 Management Review and Audits OH-11 1
2.5 Training and Qualification QM-11 1
3.0 CONTROL OF DOCUMENTS AND RECORDS OM-12
-1 3.1 Preparation of P r ocedu're s OH-12 1
3.2 Document Control OM-13 1
3.3 OA Records OM-14 1
4.0 CONTROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES OM-16 1
4.1 Purchase Orders OM-16 1
4.2 Receipt Inspection QM-16 2
5.0 CONTROL OF ACTIVITIES OM-17 1
5.1 Sample Control QM-17 1
5.2 Anal ytical Qual ity C ontrol CM-17~
1 5.3 Data Review and Processing OM-18 1
5.4 Research and Development of Special Procedures OM-19 1
6.0 NONCONFORMANCES AND CORRECTIVE ACTIONS QM-20 2
7.0 AUDITS QM-21 1
e
w..o t.
ov.
ar-t;a3-U1 ATTACliMENT #7(Con:'d)
M25JANSS.NRC (Page 4 0F S )
(PAGE 77 0F 169)
-Gr
/92
.A "a nu.i l
- t. p r i l 1 9 d ',
Revision 1 INTRODUCT!UN R ad i a ti on '4anaqement Corporation was founde.! in 1969 to provi de an emergency radi at ion ~ medical program for,ejroup of major nucl ear el ec tr i c ut i l i ty cow.' an ie s in thc mid-Atlantic region.
Their mandate was to provide the facilities and trained staff needed for the eval ua t i on a nti treatment of real or suspected r ad iat ion injuries.
Fr ota this original focus RMC's caoabilities have broaden?d to include the surveillance of the environmental impect of tne t ec hnol oq ic al and industrial world in which we live.
RMC is organized in a functional manner to provide medi c al, nucleir, analytical, and environmental services.
It is important for RMC to perform this work correctly and accordinq to contractual and regulatory requirements.
RMC management has established thi s Quality Assurance Program to provide the col ic ies, goals, and objectives of the Corporation.
The reauirements of RMC customers for formal doc umen ted ou al i ty assurance programs vary from the stringent, formalized requirements of the nuclear industry for safety-related i tems to non-speci fied. requirement s o f the commercial industry.
This Quality Assurance Manual is intended to establish the basic policies and requirements of all work without imposing unnecessary requi rements on the activities performed for tho,se customers with,less stringent requirements.
RMC procedures inipl emen t the program and the detailed requirements of specific customers.
The organizational structure of RMC and the respons i bil i t ies for impl ementat ion of this Qual ity A ssurance Manual are described in Section 1.0.
The general requirements of the Ouality Assurance Program are contained in Section 20.
Impl ementation of the Qual ity Assurance Program requires l'
procedures and instructions.
The requir ements f or control of these procedures and instructions and the maintenance of records are in Section 30.
Sec tion 4 0 is the requirement for assuring that l
purchased materials, equipment, and services are specified l
(
09-1 i
ATTACitMENT #7(Cont'd) p O25JAN85'.NRC' (Page50FSj)
NfAGE 78 0F 169)
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- .i n 4 i l I. i e r i 1 l'-34 Liv i s i ois 1 in the procurement documents, and that the delivereI items
-meet the requirenesets of the procu rerren t docun erit.
[
The reauirembnts for controlIing the activities and 4
services of 4MC are contained in Section 5 0.
Sections 6.0 and 7.0 des cr i be the requ i rerren t s for r epo r ti ng activities.not being performed to RMC qualit y standards and corrective ac tions, and the performance and reportino of internal audits.
i e
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..,.,m ATTACHMENTJ7(Cont'd){v')
( lR25JAN85.NRC (Paf,e 6 0F 80)
*(PACE 79 0F 169) 52
/4)
JA M a nu a l A:)ril 1994 R-vision 1 STATFMENT OF POL IC Y AND. AUTHORITY DMC 's corpora te objec ti ve is to render to each of our c l i en ts the best pussible orofessional consulting, a na ly ti c al. and medical services.
PMC will provide its customers with consulting, anal y ti c al, qeneral support, and medical servic's that meet the professional standards of our customers in industry and Government.
This manual is the Corporate guideline for all our employees to assure that client quality objactives are met.
~
Ouality Assurance involves everyone i n - the conipany and every person nas respon s i b il i ty for the Qual ity of the part of our product that he or she helps produce.
Quality is the respons ibil'i ty of each manager, supervisor, and employ ee.
The Manager, Quality Assurance is the staff member that oversees qual ity for the Corporation and helps mana Jers maintain control of their activities.
~
It is tne pol icy of RMC to perform our work.in o quality manner and to compl y wi th the cont ractual requirements of our customars.
l The Presi dent / Chief Executi ve Of fi cer of the Company has full responsibility for the performance of the sork performed by RMC personnel.
The Manager, Qual ity Assurance, has been delegated the work,of establ ishing and maintaining the Corporate Quali ty Assu rance Program of. R'1C.
The Manager, Qu al i ty Assurance, has, through this delegation, the authority and organizational freedom to:
- a. verify through audits, surveill ance and inspections the impl ementation of the Program; b.
identify quality'problemsl c.
initiate, recommend and provide solutions; and
- d. take necessary correc tive ac tion, including work stoppage, where necessary to. assure satisfactory impl ement'at ion of the Program The effectiveness of apy Quality Assurance Program is dependent upon the individual s who implement the Prograin.
04-3
ATTACIDIENT #7(Cont 'd) f'%-
)25JAN85.NRC
{
'J (Page 7 0F 80) t'PAGE 80 0F 169)
.f8
/42
') L '%s n, s :s I A:s r i I l 'd ' 4 u.tvi s ion' 1
.Accordingty, alI employees of RMC must Compl Y Wi ti' the r equ i r ernent s o f this Juality Assurance Program.
t.1 I niembe r s of nanagement snus t give full support to maintaininq an
~
ef fective cual ity program as defined in this Ma'1ual.
When problems or differences of opinion.cannot ~ be resol ved - wi th i n.the oroani z at ion, they will.be brought to l
the attention of-the President / Chief ~Executi ve Of t icer for final r esol ut ion.
+
7/6/84 Date R.
T.
McKernan l
President / Chief Executive Officer e
t I
O D
G e
0 0
i C:4-4
~
G v.
ATTAOD!ENT #7(Cont'd) O
~('125JAN85.NRC i
(Page 8 0F 88')'
PAGE 81 0F 169)
?
S1
/92
- A N nuai April 1914 aevision i 1.0 1R G A *ll l A T ! Die AND RESo0NS!b! LIT!!S It is the policy of RMC to provide each cl ient the best possibl e prof essional consulting, analytical, general support, and medical services. To i mpl emen t this policy RMC has a corporate organization managed and s ta f fed by quali fie d and competent professional p eopl e.
The general structure of this organization i s. illustrated in Attache.ent
- 1..The responsibilities or functions of the organization are described below.
1.1 D r es i den t /C h i g f_Ex ggu1Lvg_O f fig gr The President establishes the policies, goals, and objecti ves of - the C orporate Qual it y pro:Jram.
He assures i ts ef f ec tiveness through this Quality Assurance Drogram.
The President provides full support to thee Manager, Qu al i t y Assurance in implementing this OA Manual.
1.2 Dresid2011_hadiSd1_12EYiSR1_DIXili2D_
The President, Medical Services Division reports direc tl y to the President / Chief Executive Officer.
He is resoonsible for the policies and requirements of the medical emergency support services provided to RMC customers and to provide these services in a professional manner.
The-President, Medical Services Division gives his full support to the qual i ty assurance requirements set fo rt h in this Quality Assurance Manual, assuring compliance to the full est degree by hi s staf f.
1.3 General Manager, Environmental Services Di_ vision The General Manacer, Environmental Services reports di r ec tl y to the President / Chief Executive Of ficer and is responsible to provide environmental and related analy ti cal services of RMC.
The General Manager, Environmental Services gives his full support to the quality assurance requirements set forth in this Quali ty Aisurance Manual, assuring compliance to the fullest degree by his staff.
Qv. - 5
p)
{A25JAN85.NRC jCENSE NO. 37-13129-01 ATTACID!ENT #7(Cont'd) (
(Page 9 0F SE)
(PAGE 82 0F 169) h
-40
/42 JA Scinu a l Aaril li t4 Rsvisicn 1 Tne General "anager, Environmental Services Division utilizes the following management staff members in carrying out his resoonsibil-ities:
Manaqers. Environmental Services Manager, Environmental Chemistry 14 G20gral Managet1_Nucl2dr_Serviggi_giviliDD The General 'ianager. Nuclear Services reports directly to the President / Chief Executive Officer and is responsible to provide the nuclear and related anal y ti c al services of RuC.
The General Manager, Nuclear Services cives his full support to the qual i ty assurance requi rements set forth in this ?uality Assurance Manual, assuring compl iance to the fullest decree.by his staff.
The General Manager, Nuclear Services Division utilizes recional office managers in carrying out his responsibilities.
1.5 Mananer, Ga al i t y_ A s s u r a nc e The."anager, Quality Assurance reports directly to the President / Chief Executi ve Of ficer and is responsible to verify compliance to the Quality Assurance Program.
The Manager, Quality Assurance has sufficient independence from the influence of costs and schedules to effectively assure conformance to the Quality Assurance Program and l
has the authority and responsibility to
- a. Audit, monitor, inspect and evaluate activitiesl
- b. Identify quality problems and initiate, recommene or provide solutions and verify implementation of solutionsi
- c. Perform evaluations on a pl anned and periodic basis to verify that the Quality Assurance Program is being e f f ec t ivel y i mpl emen tedl and
- d. Stop work or further processing, analysis or delivery of reports or take other warranted actions as necessary on work that does not meet qual i t y standards.
G t4-6
ATTACIDIENT #7(Cont'd) Qq A nt.N5h.No. J/-1J129-01 (A25JAN85.NRC (Page 10 0F SS,)
(PAGE 83 0F 169) 4/
/4">
JA Monual April 1 7 tl 4 Revision !
The cia j o r functnons of the aanager. Qualitv t.ssurance include the following:
- a. Develoa the Corporate Quality A ssu ranc e Fanual and proc ei. ores necessary to fulfill RMC sA resnrnsibilities; b.
Provide a working inter face between RMC divisions anil other i ncus try and regulatory groups for all CA matters; c.
Issue periodic reports to the President / Chief Executive Of ficer on the status and ef f ectiveness of the Qual ity Assurance P rogr aml d.
Noti fy the appropriate Division Manager of any.
significant quality related problems or de f ic ien i es t and' provide interface.with the appropriate Manager on any items requiring resolution; and
- e. Serve as Chairman, Quality Assurance CommittecI.
1.5.1 Qual ity A ssurance Commi ttee A Quality A ssurance Commi ttee shal l be provided to ma i n ta i n commun ic a t i,on and interface between the Divisions and to assure continuity in the understanding and impl ementat ion of the Quality Assurance policies and requirements.
The Committee members shall be the Manager of Quality Assurance, Divisidn Coordinators of Quality Assurance and other RMC personnel as needed.
The Committee shall meet at least once each cal endar quarter.
Minutes of Committee meetings shall be prepared and sent to Committee Members and all Division Managers.
1.5.2 Divis ion Coordinators o f Qual i ty Assurance (DC0A)
DCQA's are recommended by the Division ManaQers and appointed by the Manager of Quality Assurance.
The major functions of the DCQA's are to:
a.
Support the activities of the Quality Assurance Committee by attendance at Committee meetings 04-7
41Londt av,
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and cooperating with the 'ianage r, %uality As5urance on matters, as requestedl
- b. Coordi,nate alI audit activities within the Division; l
- c. Periodically evaluate the implementation of the Quality Assurance Program by the Division.snd report to the Manager, Quality Assurance; and
- 1. Review and concur with all Civision procedures.
1.5.3 Document Custod ian i:
Document Custodian (s)- is responsiole for mJintaining and Controlling the storage and distribution of records (for example, OA
- 4anual, orocedures) generated as a result of implementation of the Quality Assurance Program.
A Document Custodian may be assigned to.each Division, to each of fice, as a single Corporate Document Custod ia n, or any combination thereof.
The Manager, Quali ty Assurance will assign Docunent Custodians.
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AT TACIDiEST # 7 (Con t ' d) (
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I 63 14 7 JA Minual A;>r i l 1494 Rev i s i ori 1 2.0 OUALITY ASSURANCE PRUGPAM 21 General The RMC Quality Assurance Program has been esta*>lished to control the activities performed by d.MC persunnel.
Adherence to~the requirements of the' Quality Assurance Progran is mandatory for all RMC personnel.
This Corpora te Uual it/ Assurance Manual is the nighest level document which describes the Quality Assurance Program.
Any conflicts, which cannot be resolved at the Department or Div is ion l evel, r egarding i nte rpretati on or implementation of thi's Manual shall be promptly reported to the Manager, Quality Assurance for resolution.
If satisfactory. resolution cannot be
[
reached the President / Chief Executive Of ficer sha,ll be consulted for final determi nat ion.
'.2 Scope 2
This' Quality Assurance Manual describes the_oolicies, goals, and objectives necessary to assure that work is performed in a qual i ty manne r.
The program described is applicable to all' cl ient work performed by AMC.
.The purpo se o f thi s Manu,a l is to establish the principles that provide the level of qual ity appropriate to each activity.
It i s recognized that the deJree of manaoement control of cuality assurance to be applied v ar i es from Division to Division and from project to project.
When specific customer requirements are specified they shall be met in all cases.
When specific customer requirements are not specified the work s ha l l be performed in a professional and quality manner using the requirements of this Quality Assurance Manual as a gui de.
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f)CENSENo. 37-13129-01 ATTACHMENT #7(Cont'd)
N R25JAN85.NRC (Page 13 0F 88)
(PAGE 86 0F 169) 44
/4) s % nual A;iril l 'M 4 Revision 1 2.T Suality Assuranca "anual Control 2.3.1 Approval This Manual includes a Statement of Policy which is signed by the President / Chief Executive Officer. The Statement of Policy provides authorization and evidence of manaqement committment to the Quality Assurance Program.
This Manual, and all changes thereto, shall be l
approved by the President / Chief Executive Officer, and shall be reviewed for concurrence by the following:
President, Medical Services
-General Manager, Environmental Services General Manager, Nuclear Services Manager, Quality Assurance e
2.3 7 Dis tribut ion Oistribution o f Manuals will be. accomplished by the responsible Document Custodian in accordance wi th Sect i on 3.2 (Document Control) of this I
Manual.
2.3.3 Revisions Each Manual, page is identified with the applicable r ev i s i on.
Additions,. deletions, or changes to the Manual constitute revisions.
Revisions will be made by sec t ion s.
Revisions will be designated by the next number following that of the superseded revision.
With the exception of a comolete revision to the entire Manual in'which virtually all pages are affected, revisions will have a vertical line in the mar gin adjacent to tne paragraph revised.
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(PAGE 87 0F 169)
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..' A M a n u.*l Aprii 11 fD, P e v i s i osi 1
?.3.4 E f f ec tive Date of Implementation The original issue and all c han ejr? S to thi s Mariu s i shall'be,i nc o r po r a t ed in the implementing Drncedures within 9d days of the issuance date of the Manual unl ess an interim action pl ari is approved _by the Manager, Cuality Assurance.
2.4 Management Review and Audits 2.4.1 Audits of the implementation of the,QA Prograin will be conduc ted in accordance with the requirements of Section ~ 7.0 of this "3nual.
2.4.2 Management Reviews:
The Manager, Qual i ty Assurance Drepares and submits a report to the President / Chief Executive Officer on an annual hasis on the status and adequacy of the OA
~
Program.
-2.5 Training and Qualification Der s onn el pe rforming cl ient work according to established procedures shall be trained and qualified to perform their assigned dutles.
Records of all training or qualification will be maintained in the "ivision or Department responsible for the training.
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1 3.0 COhik3L OF DOCUMENTS A*.C ?EC;RDS 3.1 " reparation o f Procedures This section describes the meosures use: by R.MC to issure that all procedures for work performed f.o r clients are approved, provided, and used.
3.1 1 Procedures and revisions will be prepared in
=
accordance with the requirements of a written procedure, and will provide applicable requirements, information, instructioas and controls, to assure that the_ governed activity is s at is f ac tor il y accompl i shed.
Proceoures will be prepared, as needed, by each Division and shall be identified by the prefix letters as follows:
O series - Quality Assurance Depart mant 2
e M series - Medical' Services Division N series - Nuclear Services Division E series - Environmental Services Division 3.1.2 Procedures will be reviewed and approved by representative per sonnel who are responsible for implementation and by the designateo Division Coordinator of QA (OCOA).
Final approval of the procedure is the responsibility of the apt >ropriate Manager, as follows:
0 series - Manager, Quality Assurance M series - President, Medical Services N series - General Manager, Nuclear Services E series - General Manager, Environnental Services 3 1.3 P.evision of Procecures requires the seme extent of reviews and approvals as the orioinal issue.
3 1.4 Interim changes to procedures can be made with the authority of the Project Manager or higher responsible person.
These changes may take the form of margin or insert changes.
Such changes snall be i ni t i al ed and dated.
If the changes are to be applied in $bbsequent work, they must be subjected to the normal review and approval OM-12 l
n ICEt!SE NO. 37-13129-01' ATTACID1ENT #7(Cont'd) Q V R25JAN85.NRC (Page16OF8p)
(PAGE 89 0F 169)
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/47 JA Manu i t April l '7 A 4 R vision 1 process which will then result i n.s revise 1 procedure.
3 1.5 Special ins truc ti cni r el at ive to an aporoved procedure or for spec i fi c cl ient work may be use*.
These i ns truc t i ous are approved, datod an1 si.3ner "y the Project Manager er higher resoonsible person.
3.2 Oncument Control This section describes the system used to centrol the i ssuanc e and distribution of documents such as this OS
- anual, procedures and revisions, and special instructions to assure that the latest versions are being used.
3 2 1 Documents will be distributed as Controlled or Uncontrolled copies.
Recioients of Controlled.
copies will be sent subsequent revisions.
Recipients of Uncontrolled copies wi.13 not be'sent rev is ions and their copies ~will only be effective at the time of distribution. 'Only Controlled cooles will be issued to RMC personnel.
3.2.2 The user of documents is responsible for assuring that the latest issue of the document is being used and that voided, superseded, or obsolete documents are not being used.
3.2.3 Documents will be issued by a Document Custodian es follows:
(a) The Document Custodian shall verify that the proper reviews and approvals have been obtained prior to distribution.
(b) Documents to be issued for implementation shall be labeled as " Controlled".
Only documents l abel ed "C ont r ol l ed" shall be used for implementation.
(c) The Document Cus todian. will establ ish a li st of " Controlled" copy recipients.
Each copy will be identified and registered to the recipient by,hame, conpany affiliation (if GM-13
p tor.Ndt,bu. J/-13129-Of ATTACID!ENT #7(Cont 'd)
Q 25JAN85.NRC (Page 17 0F 8S)'
(PAGE 90 0F 169) 68
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- 1 l'394 Revision 1 other than RMC), date issueu. and revision of the document bein-) issued.
(d) All Controlled copies will be issuec via a document transmittal with return receipt ac k nowl edg eme n t requested.
(e) If the return receipt acknowledgenent has not been received within a reascnable time, the Document Custodian will advise the Manager GA who may take action as appropriate, such as issue notification to stop work, obtain the ack nowl edgemen t form or remove the docur.ent from controlled status.
(f) The Document Custodian will ma.intain aporopriate distribution-end master records for each document that he issues.
3.3 Quality Assurance Records 3.3.1 Each Divis ion or Depar tment is responsible for the.
maintenance and. retention of quality related records that it generates.
Within this
-responsibility, each shall provide appropriete filing and storage for their records.
All records shall be legible, identifiable and retrievable.
3.3.2 QA records to be maintained include but are not l i mit ed to the ful, lowing (as applicable):
Drocedures and Manuals
- Training documentation
- Audit reDorts and responses Sample control documentation Analytical control records Reports to management on the QA program Cal ibrat ion cer t.i ficates 9
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21 *ano.i t Auri1 l'J 4 4 D*Vi5 ion 1 3.3.3 "decord Retention 0.ecords shall be retained per client specificatiens.
In 1 leu ci clsent' specifications records will be retained for a reasonable period appropriate to the nature o f the record.
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ATTACli31ENT #7(Cont'd) d flCENSENO. 37-13129-01
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eA Manua1 Nh25JAN85.NRC (Page 19 0F 88)
June 1984 (PAGE 92 0F 169)
V Revision 2 Jo
/f) 4.0 C ONTROL r1F PURCHASED MATERIAL, t-3 U I P P E N T. AAD SERVICES This section desc r i be s the requirements for control of materials, equipment, and s ervices ' hich are purcha:.?d for use in ac tivi ties wi thin the scoce of this Qual.ity
~
Assurance Manual.
4.1 Purchase Orders 411 Purchase Orders, when used will identify the technical and quality requirements as necessory to assure that the proper items or services are provided.
4 1.2 Cer ti ficat ion, when - requi red to be provided with the shipment, will be i denti fied on the Purchase Order.
4 1.3 Requirements for docun.entation or traceability shall -be speci fied, where applicable.
4.2 PeCeip t Inspection Items will be inspected for shipping damage, quantity, proper identification or l abel i ng, and specific Purchase Order requirements.
Items which are ace ?ptable will be appropriately stored or moved to the locat ion where they are used.
For items which'are damaged, incorrect, or lack the required documentation, they snall be identified as unacceptable and stored until disposition l
Is determined.
A Nonconformance Report will be initiated if the unacceptable item is a safety-related item that could affect the saf ety of RMC per sonnel or others that may use the ' item.
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37-13129-01 ATTACHMENT #7(Cont'd) Q V] CENSE No.
23JAN85.NRC (Page.20 0F 88)
(PAGE 93,OF 69) y JA M:e nu a l Auril 1964
%3 vision 1 5.n CONTROL OF actis! tic 5 RMC, in its var,ious act ivi ties provides anal yti cal services both qualitative and quantitative, to many of its clients.
To be of value, these measurement services must meet industrial norms.
RMC, as a matter of policy, will use acceoted industrial / scientific standards where they aro applicable.
~
5.1 Sample Cont rol To assure consistency and continuity in the work ruutinely performed, each Division or Department engaged in anal ytical measurement services shall develop and implement procedures appropriete for controlling the sampling process.
These procedures shall include provisions, steps or instructions as applicable for sample collection, handling, receipt, processing,
-storage, disposition, i den t i fi ca t i on and documentation of the sampling process.
52 Analytical Quality Control 5 2 1 Where applicable, instruments used in client work shall be appropriatl,y tested or ca l i b ra te:1 and maintained.
Each Division or Department shall identify the instruments to be tested, the test elements and frequency each i nstrument is to be tested, and provide documentation for the instrument controi ac t i v i t i e s.
In testing instruments the following shall be observed:
Instruments shall be cal ibrated against appropriate standards.
Instruments calibrated at weekly, monthly or greater intervals, shall' display their cal ibration status, the date of last calibration and the next calibration due date.
Other laboratory instruments shall be calibrated daily or before use and shall display the calibration frequency and identi f y where cal ibra,t ion resul ts are to be recorded.
Instruments which can not be properly calibrated shall be labeled'or tagged as "Out-of-Order" (or OM-17
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4.ivisiCM 1 equiva)ent).to prevent their use unti l sufficient repairs, etc. and rec al i br at ion results permit their r ets se.
Instrument records shall be traceabl e tu the instrument by manufacturer model and serial
- number. Droperty number or other identifier affixed to the i nstrument.
S.2.2 Each Division or Depar tment pert ormin, routine laboratory analyses (i.e.,
physical, c he mi ca l,
b lochem ic al, or bioassay) shall es tabl i sn procedures, or sections.within existing orocedures, to control the sample anal ys i s proces!.
These procedures shall include Drovisions or i ns truc t ions as appl ic abl e for*
- Controlling qual ity of laboratory services provided (e.g. distilled and other specially prepared water); glassware; reagents, solvents and gases; and standard reference mater ial s used in the analyses.
- Controlling anal ytical performance through the use_of appropriate laboratory standards.and control samples and as applicable, interlaboratory comparisons.
5 3 Oota Review and Processing i
Data collected, processe'd and reported to cl ients shall be appropriately reviewed for correctness and reasonableness.
5 3.1 Sach Division or Department engaged in data coll ection activities shall be responsible for reviewing and processing data that it collects in work performed for clients, and for documentino data review ~and processing activities.
5.3.2 Supervisors or other responsible personnel shall check a fraction of the resul ts of hand computations performed by technicians.
Checkejd results shall be i nitial ed by the individual per f orm ing the check.
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5.3.3 Computer programs.and revisions orepared
's y. R i> C Shall be - i den t i fi ed, v er i fi ed and documented.
Documentation shall include a listing of the program and test' data (if applicable).
Program output shall be traceabl e to the speci fic prograrr or revision level.used.
0 5.4 D.es ea rc h and Development of Special procedures Special analytical procedures developed by RMC shall be cual i f i ed to verify their adequacy.
Verification and documentation shall be done by a person oth.,*r than tha person who prepared the procedure.
If research procedures are to be used for client work, they shall be clearl y identi fied to the C1ient as procedures' under development.
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'125JAN85.NRC June 1984 (PACE 96 0F 169)
N Revision 2 21
/f 7 5 0 NONC GNFOR MANCE S AND C CRREC TIVE ACTICNS 6.~ 1 It is.the respensibility of all RMC personnel to c onduct their work in accordance with established standards and requirements.
A nonconformance is defined.ss: a deficienc y in characteristic, documentation, or orocedure which results in a_materiale part, component, or activity being in disagreement with established oual it y assurance or implementing procedural requirements such that-the quality of the mis ter i al,
part, component, or activity is rendered unacceptable or indeterminate.
Examples of nonconformances i ncl ude:
physical defects, test failures, or omissions, incorrect or inadequate documentation; departure from purchase document or specification ~ requi rements, or' departure from prescribed Drocessing, inspection, install ation, or test procedures / documents.
6.2 It is tne. responsibility of any individual noting a nonconformance to report the c ond i t i co in accordance with.the requirements of procedure Q6 " Reporting of Defects and Nonconf ormances".
6.3 All reported deviations (nonc~nformances), whether empl oy e e-r epo r t ed, uncovered through internal audits or c l i en t, audits, shall be reviewed by management in accordance wi th the procedures outlined in procedure 06.
Corrective actions shall be implemented, if warranted, by the group / party specified by management on the Nonconf ormance Report as described in procedure Q6.
6.4 Documentation of nonconf ormances 'and act ions taken to i
correct them shall comply tu the requirements s t ipul at ed in procedure 06.
Documentation shall include:
a) Description of the nonconformance, date of identification and initiator of the report.
b) Evidence of review by the manager responsible for the activity.
c) Actions r equired to resolve or correct the nonconformance and to prevent reoccurrence.
d) Identification or group / party responsible for implementing corrective action.
e) Requirements for notification of clients for nonconformance.
f) Accep tance and ve r i f icati on o f correc tive ac t ions and close out of the nonconformance by the Manager of QA.
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JA M.snu s 1 April 19'14 ouvision 1 70 AUDITS 71 Internal audits of R MC 's Quality As sur esnce pr ogram shall be conducted:
To verify that the elements and requirements
~
described in this Manual have been approDriistely developed, implemented and docunented;
- To identify those items in the 7A progrsm which have not been sufficiently developed, i mpl emen ted or documented and which requi re evaludt ion and corrective actions; and
.To verify that correc tive ac t ions have acen taken where indicated.
7.2 The Manager, QA is responsible for the coordination and performance or sudtts end,
e subsequent ~ follow.up actions.
7.3 Audits shall be. performed by the Manai}er QA or other qualifled individuals who are f amiliar with,
but not directly responsible for the work activities being audited.
7.4 Audits shall be performed and the results documented in an audit report in occordance wi th the requirements of a:1 approved written procedure.
Management of the' audited Division or Department shall respond to all deficiencies identi fied by the audit.
Their response shall include corrective ac tions to be taken to correct specific deficiencies and the date by which the action will be completed.
- 7. 5 Follow-up actions including veri fication of corrective actions impl e me n t ed and audit close-out shall be documented.
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Moody Aun Pottstown Environmental Environmental Ecotogical Lab Ecological Lab Chemestry Lab Consulting OA Ptuladelphia Midwest Meritten O uarnur R eiye
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PHILADELPHIA, PA 191M LICENSE NO. 37-13129-01 ATTACHMENT #7(Cont'd)
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(PAGE 99 0F 169) l' 72
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Date Stephen H. Kim Executive Vice President REVISICNS Rev.hio.
Date Para.
Page Approved by Date 1
11/79 5.3.4 R9-3 11/28/79 R9-5 I
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11/79 11.0 R9-9 Controlled Copy No,_
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cnber, 1979 LICENSE NO.-37-13129-01 ATTACIDIENT #7(Cont'd)
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/$ 7 REQUEST FOR REVIEW AND APPROVAL OF PROCEDURE NO. R9 - REVISION 1 fl.' m b
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NOV o 71 tin Date Stephen M. Kim Executive Vice President i
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14,7 Procedure No. R9 Bevision: 1 Novenber,1979 RADIATI0tt PROTECT 10ft PROCEDURE
-1.0 PURPOSE The purpose of this procedure is to assure that radioactive materials and radiation-producing devices possessed by RMC are.obtained, used, stored and transferred in accordance with applicable laws and generally accepted practices governing radiation health and safety. ~This procedure also specifies steps to be taken to maintain radiation exposures and releases of radioactive materials in effluents-to unrestricted areas as far below the legal limits as practicable.
2.0 SCOPE This procedure applies to all individuals who handle or utilize radio-active materials or radiation-producing devices on premises owned or leased by RHC; and to individuals who handle or utilize such materials or devices elsewhere as authorized by licenses granted to RMC.
3.0 DEFINITIONS 3.1.
The words and phrases defined in 10 CFR 20 are applicable to these procedures, except as noted below.
3.2 Materials and Devices Materials and devices means radioactive materials and devices which produce ionizing rad'iation purposely or incidentally.
3.3 Radiation Worker Radiation worker means 'an individual who has been so identified in a list of radiation workers maintained by the Radiation Safety Officer (see 14.1-14.3).
f 3.4 Radiation Area Radiation area is any accessible area in which the exposure rate l
exceeds 2 mrem / hour.
i 4.0 EXPOSURES OF INDIVIDUALS TO RADI ATION IN RESTRICTED AREAS l
4.1 Exposure shall be restricted to doses ALARA below the limits in 10 CFR 20.101 (a).
Exposures above these limits (i.e.,1.25 rem / quarter - whole b'ody) 4.2 require the approval,of the RSO or higher level management.
4.3 Each individual who occupies a Radiation Area shall wear an RMC-issued TLD personnel dosimeter.
4.4 No individual shall enter a High Radiation Area without explicit i
authorization in the form of a Radiation Work Permit (RWP), specifying 1
R9-1
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po N7 Revision: 1 lbve:ter, 1979 date, time, place, identification of individuals; description of activities, monitoring equipment, personnel dosimetry and protective clothing required. The RSO or his assistant shall-approve all RWPs.
4.5 The vendor who supplies TLD personnel dosimeters shall be requested to provide R!1C with imediate notification of TLD readings of I rem or greater.
4.6 TLD personnel dosimeters shall be exchanged at least quarterly.
4.7 TLD personnel dosimetry reports shall be inspected by the RSO or his assistant within one week of their receipt.
Inspection shall be confirmed by date and signature of RSO or his assistant.
4.8 The RSO shall investigate and report to the Executive Vice President each quarterly exposure in excess of 100 mrem. He shall also make inquiries concerning each unusual exposure.
This would include exposures exceeding twice the usual magnitude or beta or neutron exposures that would not be expected as an ordinary result of the individual's job assignment.
4.9 The RSO shall keep the NRC Form 5 and enter the exposure information from the TLD service on the record within one week of receipt.
4.10 If a Radiation Worker's TLD should be lost or the reading invalidated, the RSO and the worker shall estimate the maximum probable exposure incurred by the worker during the unmonitored period of time.
The worker's exposure record shall be notated that it is an estimate, and shall be initialed by the worker and the RSO.
4.11 Any employee who requests knowledge of his/her exposure shall be given a written report of his/her exposure up to that date.
4.12. Exposure of minors (an individual under 18 years of age) shall be con-trolled in accordance with requirements of 10 CFR 20.104, 5.0 EXPOSURE OF INDIVIDUALS TO CONCENTRATIONS OF RADI0 ACTIVE MATEP,IAL IN RESTRICTED AREAS 5.1 Exposure of individuals to concentrations of radioactive material in air, in restricted areas, shall be limited as specified in 10 CFR 20.103.
5.2 These limitations shall be achieved by adherence to the following pro-cedures and practices:
I 5.2.1 Radiation workers shall be trained as specified in Section 13 of these procedures.
5.2.2 Radiation workers shall be supervised by those individuals identified in our NRC license.
5.2.3 Incomir.g shipments of radioactive materials, other than waste, shall be inspected in accordance with Sections 10 and 11 of these procedures.
ATTACHMENT #7(Cont'd) n25JAN83.NRC
-(Page 30 0F-83) y
-tPAGE 103 OF 169)8 /
N7 Pucedure Ib. R9 Favision: 1 lbv # E, 1979 5.2.4 Radiation workers shall be provided with adequate facilities and equipment to handle, store and dispose of radioactive '
ma terial.
5.2.5 Handling procedures which may result in airborne concen-trations exceeding 1/10 of the concentrations listed in Appendix B, Table 1 Column 1,10 CFR 20 shall be conducted
'n fume hoods or in glove boxes. This would include the evaporation of liquid samples and vacuum pump discharges whenever a vacuum pump is being used on a sample containing radioactive material.
5.2.6 Particular precautions should be taken with high specific activity materials, especially alpha emitters. These materials shall be handled in a fame hood or glove box.
5.2.7 Radioactive waste shall be disposed of in accordance with Section 7.
5.3 Exposure Control - program 5.3.1 Periodic contamination surveys as specified in Section 6 of these procedures shall be conducted.
5.3.2 Each radiation worker shall be given a preplacement whole body count and/or submit a baseline urine sample to be analyzed for 8H and mixed fission products minus K-40.
5.3.3 Each individual who knows or suspects that he/she or another individual has been exposed in excess of the 40-hour limits of 10 CFR 20.103 shall report the cir-cumstances of the exposure to the RSO or his assistant 1
without delay.
5.3.4
'The bioassay program for all workers involved in the processing of tritium and/or I-125 and/or I-131 ~shall be performed in accordance with " Guidelines for Bioassay Requirements for Tritium". Nuclear Regulatory Comission, Division of Fuel Cycle and Material Safety. October 19, 1977, AB/REA and Regulatory Guide 8.20, "Applica.tions of Bioassay for I-125 and 1-131", Revision 1. September 1979.
Rev. 1 Nov. 79 NOTE: Because the quantities processed by an individual at any one time or the total amount processed per month for tritium and three months for I-125 and/or I-131 are less than 10% of the levels in Table 1 of the above Guideline and, Guide during normal operations, bicassays will only be performed under circumstances exceeding these limits.
5.3.5 P.adiation workers shall monitor their person upon leaving their work area and before leaving the restricted area.
R9-3
v e-n-
--m-w,,
ATTACID!EST #7 (Con.t 'd) O a(PAGE1040F16,9]
sx;8sanc (Page310F.8p)
Y Prcoedur#bb. 'R9 e
Revision: 1 Nowmber,1979
(.
Food and beverage consumption and smoking are prohibited 1
5.3.6 in restricted areas.
Rubber or plastic gloves should be worn when handling radio-l 5.3.7 active materials.
All procedures involving the non-routine use of handling 5.3.8 radioactive material will be submitted to the RSO for review before the procedure is instituted.
Any worker who finds a concentration of contamination in 5.3.9 on his person will imediately 2
excess of 1000 dpm/100 cm
/
report this finding to the RSO.
1 Each circumstances of possible overexposure which comes 5.3.10 to the attention of the RSO or his assistant shall be investigated; the report of investigation shall be sub-mitted to the Executive Vice President.
i 6.0 PERIODIC SURVEYS In the conduct of the survey specified below, the H.P. Technician r
6.1 shall take such imediate action as he deems necessary to correct or prevent a radiation hazard. He shall report all unsafe or l
l unusual findings to the RSO without delay.
Surveys of Radiation Levels in Restricted and Unrestricted Areas _
6.2 Upon specified frequencies, or when conditions have changed,
- 6.2.1
. a survey of each designated area of the building shall be conducted.
An instrument calibrated to measure the radiation emiited i
6.2.2 l-by the radioactive materials and devices shall be used.
The H.P. Technician shall not expose himself unnecessarily 6.2.3 to obtain a measurement of a manifestly hazardous point or I
l The H.P. Technician shall use a prepared Radiation area.
At locations Survey Fom to record all survey findings.
j where exposure rates exceed 1 arenVhour, he shall show the i
exposure rate at contact and exposure rate at l'.
l The report shall show exposure rates measured at perimeters l
6.2.4 of radiation,in a high radiation area, and shall note whether 1
these areas are posted and secured in accordance with 10 CFR i
20.203. The proper signs will be posted if needed.
6.3 Surveys for Removable Contamination Upon specified frequencies, except for the waste storage 6.3.1 area which is surveyed each time waste is handled, a con-tamination survey shall be conducted in each designated F
room or area by the H.P. Technician.
j.
R9-4
'"'- N
"."N R C ATTACllMENT s7(Cont'd)
R25JAN85 (Page 32 0F 8,8)
(PAGE1050Fj69) f Procedu/o#tb.1P Revision: 1 tbvmber, 1979 6.3.2 Surveys for removable contamination shall be made by swiping dry filter paper discs over approximately 100 cm (4" x 4") area. The discs shall be assayed for 2
alpha-beta radiation on a gas-flow proportional counter.
6.3.3 Swipes made in tritium-handling areas shall be counted in apparatus suitable for the measurement of soft beta radiation.
6.3.4 A sufficient number of swipe points shall be selected in order to obtain a sound evaluation of the contamination status of each room or area.
In general the number of survey points will be governed by the operation conducted in the area.
2 6.3.5 Contamination levels above 100 dpm/100 cm of beta-gama radiation or detectable activity of alpha radiation shall not be allowed.
of beta-gama radia'cion 2
6.3.6 If levels > 10,000 dpm/100 cm or 100 dpm/100 cm of alpha radiation are found, the 2
RSO shall be notified insnediately.
Rev.116.4 Refer to Procedure T-53, " Radiation Surveillance Procedure" on Nov.79/
minimum survey frequencies and survey details.
7.0 WASTE DISPOSAL 7.1 Liquids containing radioactive material in concentrations not greater than the limits specified in Table II, Column 2 Appendix B,10 CFR 20 may be released to the sanitary sewage system, upon approval of the R50, if it is soluble or if no more than one l
Curie per year is released.
l 7.2 Liquids containing radioactive material in concentrations greater than the limits specified above shall be placed in a closed un-l breakable container and labeled, " Radioactive Waste". The label l
shall show the identity and approximate activity of the principal radionuclides, and the identity of the individual who placed the waste. When the container is approximately half filled, the liquid waste shall be neutralized (if applicable) and then poured into a double wall liquid waste shipping drum. The information l
on the label shall be transferred to the radioactive waste list i
as specified in 5 7.7.
7.3 Each laboratory or area'in which unsealed radioactive material is used shall have a radipactive waste receptacle.
The receptacle l
shall be labeled CAUTION RADI0 ACTIVE MATERI AL. The receptacle r
l shall be lined with a plastic bag.
1 7.4 Solid waste shall be placed in radioactive waste receptacles l
provided. Waste that may become resuspended in air (e.g.,
R9-5
p t cedure to. P3 t.ac.or. av. ai-natzv-Ut (dM_
d RR25JAN85.NRC ATTACHMENT #7(Cont'd)
N, sion: 1 (Page 33 0F 8,5)
(PAGE 106 0F 169)
?bvator,1979 4
??
/42 dusts, dust-laden filters) shall-be sealed in plastic bags before discarding to radioactive waste receptacles.
7.5 Radioactive waste shall not be compacted in the receptacles.
7.6 The plastic bags lining the radioactive waste receptacle shall be tied closed pt lor to transfer to the Radioactive Waste Storage Area.
7.7 A radioactive waste list shall be maintained in the vicinity of each radioactive waste receptacle. When the waste is transferred to the Radioactive Waste Storage Area the list shall be delivered to a designated location in the Storage Area.
7.8 Any waste showing an exposure rate of greater than 1 mR/ hour at l' shall be delivered directly to the Radioactive Waste Storage Area.
7.9 The H.P. Technician shall assure that the following conditions are met'in the Radioactive Waste Storage Area:
- The area is posted CAUTION RADI0 ACTIVE MATERIAL and CAUTION RADIATION AREA.
- The exposure rate at 36" from any drum, or item not drunined, does not exceed 10 mrem / hour and any drum does not exceed 200 mrem / hour on the surface.
- The fixed and. removable contamination levels are maintained as low as practicable but not greater than 1000 dpm cm for alpha contamination.
- All items liable to generate airborne radioactivity are sealed.
- The area is uncluttered.
- Any inconvenient or unsafe condition is brought to the attention of the RSO.
Two days prior to the transfer of waste drums to the radioactive 7.10 waste disposal vendor, the H.P. Technician shall follow the following procedure:
7.10.1 Make sure the information on the radioactive waste list for each drum is complete.
7.10.2 Seal each drum'with the band, nut and bolt provided with each drum.
7.10.3 Perform a swipe survey of each drum to assure that the re-movable contamination does not exceed the following limits:
R9-6
LICENSE NO. 37-13129-01 ATTACHMENT #7(Cont'd)
RR253AN85.NRC yWe W. M (t' age h or ef)
(PAGE 107 0F 169)
Pcvision: 1 Ncvenber,1979 pg y)
Contaminant Max. Permissible Level
'2
- 2. All other beta-gama 220 emitting radionuclides
- 3. All other alpha-emitting 22 radionuclides i
7.10.4 Uta a survey meter with a probe to measure the exposure rate at surface and at three feet for each drum.
7.1F 5 In accordance with CFR Title 49 Section 173.399 and 173.414, select the labels to be put on each drum based on the survey results obtained from 7.10.4.
7.10.6 Fill out the radioactive shipment and disposal record form supplied by the radioactive waste disposal vendor.
STORAGE OF RADI0 ACTIVE MATERIAL,
8.0 8.1 Radioactive material shall be stored in designated storage areas in accordance with the requirements of this section.
'i
- 8. 2' Each container enclosin'g radioactive material in storage shall bear a durable, clearly visible label identifying i
the radioactive contents, assay and date of assay.
It shall bear the radiation caution synt>ol and the words CAUTION i
RADI0 ACTIVE MATERIAL.
lh 8.3 Material placed in storage shall be contained in a sturdy vessel of a size and shape that permits convenient and
[
i I economic shielding and maintenance.
)
9.0 CAUTION SIGNS, LABELS, SIGNALS AND CONTROLS i
{
9.1 Caution signs and labels shall b,e used in accordance with the requirements of 10 CFR 20.203, with the following exceptions:
p
',1 9.1.1 At least one,back-up signal / control system shall be s
employed to augment the primary security system for
,5 prevention of exposure in high radiation areas.
- ),
lE s
t R9-7 i
LICENSE NO,37-131,/ N O)
)
ATTACHMENT #7(Cont'd)
RR25JAN85.NRC v
(rage n or 88)
(PAGE 108 0F 169) Procedure !b. R9 f'd
/g7 Pavision: 1 tbve:ter,1979 10.0 PICKING UP, RECEIVING AND OPENING PACKAGES OF RADIDACTIVE MATERIAL
~
10.1 Procedures for picking up, receiving and opening packages shall be in accordance with the requirements of 10 CFR 20.205.
10.2 The requirements of 10 CFR 20.205 are sufficiently stringent for health and safety purposes, but they are not sufficiently stringent for control of slight quantities of contamination which might adversely affect RMC's Quality Assurance Program.
Accordingly, the following requirements shall also apply:
10.2.1 Each package received by RMC shall be handled as if it were contaminated until such time as measurements have shown it is to be free of contamination.
10.2.2 Packages shall be monitored and opened by the radiation worker who will be using the material, or by the H.P.
technician.
10.2.3 Packages shall be monitored and opened with.n the restricted area; in a fume hood or glove box, when possible.
10.2.4 Before opening a package, radiation levels at its external surface and at 3' from its external surface shall be measured and recorded (see paragraph 13.4).
A swipe of the external surface shall also be made to assure that removable contamination in excess of 22,000 dpm/100 cm2 is not present.
This swipe shall be measured with a gas flow proportional counter.
10.2.5 If radiation levels are found ~on the external surface of the package in excess of 200 millirem per hour; or at three feet from the external surface of the package in excess of 10 millirems per hour; or the removable contamina-2 tion is found to be in excess of 22,000 dpm/100 cm, the in-dividual who has monitored the package shall proceed no further. He shall innediately inform the RSO or the assistant RSO.
10.2.6 If prohibitive radiation or contamination levels are not encountered on the exterior surface of the package, the individual monitoring and opening the package shall proceed to strip the package down to its primary container, the wrapping shall be surveyed, and if uncontaminated, discarded to clean waste.
10.2.7 If the primary container is enclosed in a radiation shield (e.g., a cyl'indrical lead shield), and the primary container can be readily removed fmm the shield by the 'use of tongs and placed in a shielded location, the inner surfaces and the outer surfaces of the tranmorting shield shall be swiped.
If the primary contais.er cannot be readily removed from the shield without incurring an exposure in excess of R9-8
' ATTACHMENT //7(Cont'd)
RR25JAN85.NRC (Page 30 vF op)
(PAGE 109 0F 169)
Pmcedure !b. 'R9 -
f pp
/./7 Revision: 1 I
tbwrt>er, 1979 5 millirem, further direction shall be otained from the RSO.
10.2.8 If a swipe' of the inner and outer surfaces of the shield shows no detectable contamination, the primary container shall be returned to the shield.
The shield shall be properly labeled.
The concerned radiation worker shall be notified for further instructions.
10.2.9 If a swipe of the inner and outer surfaces of the shield shows detectable contamination, the shield shall be dis-carded as radioactive waste or sealed in a plastic bag until it can be decontaminated. - The radioactive material shall be transferred from its original primary container to a container of suitable size and configuration for shielding.
It shall be placed in a shield; the shield shall be properly labeled. The concerned radiation worker shall be notified for further instructions.
10.2.10 If the primary container is a sealed source, see part 11 of this procedure.
11.0 SEALED SOURCES 11.1 The integrity of a sealed source shall not be violated deliberately nor shall the source be-subjected to unusual stresses without explicit approval of the RSO.
11.2 Each sealed source, or the device'in which it is permanently encased, shall be. labeled or tagged to show: the radiation caution symbol; the words CAUTION RADI0 ACTIVE MATERIAL; and the identity, quantity and date.of assay of the radionuclide.
11.3 The H.P. Technician shall maintain a card file of sealed f
sources.
Each card shall:
identify a source by radionuclide.
Rsv. 1 quantity, date of' assay and serial number; show its date of N:v.79 acquisition; and a chronological history of leak test results.
- 11.4 Sealed sources shall be leak tested in accordance with the requirements of "RC and Comonwealth of Pennsylvania licenses.
11.4.1 A leak test of a sealed source shall be performed according to the instructions in Pfic Procedure T38, Sealed-Source Leak Test Procedure.
11.4.2 No sealed source shall be ~used unless it has been leak tested f
within the prescribed interval.
11.4.3 Prior to trans'fer of a sealed source to a person (other than a waste disposal service vendor) licensed to possess the sealed source, the source shall be leak tested. A leak test certificate shall be transferred with the source.
R9-9 2-
ATTACHMENT 67(Con.t'd) '
g-hp (Pase 37 0F 8,S')
(PACE 110 0F 169) h e W. P9
)
D N7 Pavision: 1 Novatber, 1979 12.0 TRAftSFER OF LICENSED ftATERIAL 12.1 The transfdr of licensed material shall be done in accordance wi th 10 CFR 30.41.
12.2 All transfer documents shall be reviewed and approved'by the RSO prior to the transfer.
13.0 Malt 4TENANCE OF RECORDS 13.1 The following records will be maintained according to current NRC regulations for inspection by regulatory authorities:
- Receipts
- Inspection of packages
- Disposals
- Personnel dosimetry
- Transfers
- Bioassay
- Surveys
- Leak tests 13.2 Records of procurerr,ent, receipt, package inspection and transfer of material shall.be maintained.
13.2.1 If a sample is being returned to a client, it is not necessary to obtain a copy of the client's license.
13.2.2 RMC is required to comply with 10 CFR 71, " Packaging of Radioactive Materials for Transport".
One may not assume that the packaging labeling of an INC0ttING shipment is suitable for the OUTG0ING shipments.
In all cases, the shipper must identify the relevant sections of 10 CFR 71 or Title 49 before the shipment will be approved by the RSO.
-14.0 TRAINING AND INSTRUCTIONS 14.1 No individual may handle radioactive material under licenses granted to Rf1C, unless they are identified by name on the license or authorized in writing by an individual identified by name on the license.
Records of written authorization shall be retained by the RSO.
14.2 Individuals identified by name on the license shall assure that others, authorized by them'to handle radioactive material, are properly trained to conduct authorized procedures safely.
Individuals listed 6b the license and those authorized by them 14.3 to use radioactive material are referred to in these procedures as " radiation workers".
R9-10
ATTACIDTNT E 7 (Con t ' d)
R 5 h8.fiRC (Page 38 0F.8M (PACE 111 0F 169)
Procedure 16. R9
?7
/ n Revision: 'l tbvenber,1979 14.4 ~ Each radiation worker shall be given a copy of these. procedures.
~
14.5 Each radiation worker shall attend the' RMC Basic Radiation
. Pmtection Course and shall attend at least one monthly training session per year.
RMC Training Sessions are held for one hour each month.
The RSO or his assistant'shall attend these sessions.
15.0 ~ RADIATION SAFETY. OFFICER i
15'.1 The Radiation Safety Officer and his Assistant shall be appointed
~ -
by the Executive Vice President.
15.2 If the RSO should be unavailable for performance of the' duties in this section, these duties may be performed by the Assistant RSO.
15.3 He shall conduct such insp'ections, investigations, and inquiries as are necessary to obtain assurance that materials and devices are being used, stored ' nd disposed of in accordance with the a
i law and accepted practices governing radiation health and safety.
i 15.4.He is authorized to take such action, or order any RMC employee i
to take such action as he deems necessary to prevent an iminent threat to radiation health and safety.
4
-15.5 He shall supervise all tasks assigned to the H.P. Technician in these procedures.
15.6 He shall review all records-.specified in these procedures and document such review by signing and dating the records.
16.0 INVENTORY CONTROL 16.1 Since RMC is licensed to possess certain radionuclides, in certain r
quantities and foms, for certain purposes the license limits
{
shall be assured by inventory and. approval of procurement..
16.2 A physical inventory of radioactive material shall be conducted in January of each year by ~the RSO.
A' record of this inventory shall be maintained for inspection by the NRC.
16.3' The inventory shall show identity, quantity and form of radio-nuclides.
It'shall show their place of storage.
16.4 Based on_ inventory record and records of disposal and transfer, the RSO shall maintain an approximately current inventory of materials on hand.
He,shall consult the current inventory be-fore approving requests for procurement.
l 16.5 In the event that the inventerv of certain radionuclides approx-imates 80% of the authorized l emit, more exact inventory control (including computation of loss by decay) shall be exercised for those radionuclides.
i R9-11
ATTACID1ENT #7(Cont'd) O C; AGE 112 0F 169)2s~ Iri8 i
(Page 39 OF 8p)
GP 4
Decembef,*197d Procedure No.~ N1 t
GENERAL USE OF THE Cs-137 GAMMA CALIBRATOR Approved by e-e-ip Fred G. Rocco Date Inittals Vice President Technical Services REVISIONS Rev. No._
-Date Para.
Page
, Approved by Date
~
e
~., -
~
__, ~
ATTACID!ENT #7(Cont'd) p Q CENSE No. 37-13129-01 v
%M5JAN85.NRC (Page~t.0OF8p)
(PACE 113 0F 169)
'l 9
Decemoer,]1978/4)
Procedure 140. N1 GEftERAL USE OF Tr'iE Cs-137 GAMr% CALIBRATOR
- 1. 0 PURPOSE l
The purpose of this procedure is to provide instructiori for saf e and I
proper operation of the 130 Curie Cs-137 gamma irradiation source.
2.0 SCOPE
- This procedure ' describes general utili:ation of the 130 Curie Cs-137 i
gamma irradiation source and is not meant to describe usage for any particular' purpose.
3.0 DEFII4ITIONS As used in this procedure:
3.1 "Attenuator" means the devices used to redu:e the radiation beam intensity to convenient levels as necessary.
For convenience, each attenuator is denoted by its nominal reduction factor (e.g.,
the X 100 attenuator refers to that attenuator which reduces the intensity of the radiation beam by a factor of approximately 100).
NOTE: The actual value of each attenuator is a known value.
4.0 REFERENCES
4.1 Operating manual for Series 28 Calibration facilities, J. L.
Sheppard and Associates.
4.2 Radiation Protection procedures (RHC procedure R-9).
4.3 Exposure rate data for Series 20 serial number 603 irradiator.
This is a table of source output versus distance from source e
~
and attenuator used.
5.0 SAFETY PRECAUTIONS l
l 5.1 Wear assigned personal monitoring device when entering the room l
containing the irradiator.
)
5.2 When the source is exposed no individual shall cross the imaginary vertical plane that marks the area irradiated by the source. An infrared light beam with a photoelectric source interlock is j
considered to be the boundary of the area irradiated by the source.
5.3 Observe applicable radiation safety, regulations as described in reference 4.2.
5.4 The gamma survey instrument can be used to. verify that the source is inside the source housing.
i L
5.S Individuals using this source must be an authorized user.
An authorized user must be familiar with this procedure and procedure R-9 (Radiation Protection Procedures) and also must have the
'N1-1
?
pd
{V25JAN85.NRC
\\ CENSE No. 37-13129-01 ATTACIDIENT #7(Cont 'd).
(Page 41 0F 88)
(PAGE 114 0F-169)
Decemberf197[
Procedure Ho. N1 approval of the Radiation Safety Office. Authorized source users are to be listed on "PJ4C Authorized Source User and Approval Form".
5.6 Keys to the source are to be kept in a pennanent location that is not readily accessible by anyone who is not an authorized user of the source.
5.7 When the source is unlocked or in the exposed position, a chain (or rope) with' a warning sign is to be placed across the dooniay. In addition, one of the following two conditions must also be met:
- 5. 7.1 Source operator in attendance 5.7.2 Room locked
-6.0 APPARATUS 6.1 J. L. Sheppard 11odel 28-10, Serial Number 603 Gamma irradiator with nominal 130 Curies Cs-137 source.
6.2 Operational gamma survey instrument.
6.3 liotor driven specimen table with adjustable height and distance from source.
6.4 Wall mounted gamma monitoring system consisting of a detector, a remote exposure rate indicator and two red warning lights.
6.5 Red warning light above the source indicating exposure of the source when the source rod is raised.
6.6 Keys to the room, the source rod, and the calibrator.
6.7 Pho' mler tric controlled source interlock consisting of infrared light
.a cter/ receiver, reflector and electrical interlock to source controls.
7.0 INSTRUCTI0iiS 7.1 Preliminary Instructions 7.1.1 Obtain keys.and sign source utilization log.
7.1.2 Verify that no one is within the irradiation area. All operation of the source controls is to be done from behind the source.
r 7.1.3 Unlock padlock to, free source rod.
Place small key in calibrator and turn it to the right.
The source can now be exposed by raising the source rod.
7.1.4 Raise source rod and verify that red light on source is on.
7.1. 5 With the source still exposed, break the light beam marking 0367A N1-2 rm y
ATTACID1ENT #7(Cont'd) 25JAN85.NRC (Page 42 0F SA)
V AGE 115 OF 169)
'/
73 H2 December, 1978 Procedure No. M1 the boundary to the irradiation area.
Verify that the source rod drops and teminates the exposure.
7.1. 6 Check that a satisfactory performance check of the source has been done for that day.
If none has been.done, perform the required check in accordance with procedure T-18 and record the result.
7.2 Instructions Proper 7.2.1 Refer to the exposure rate data for the source (reference 4.3) for the dose rate required.
Move the specimen table to the pro'per location.
7.2.2 Set object for irradiation on the specimen table so that the center of the object is at the reference point on the 1
table top.
If necessary, adjust the height of the table to make sure the object and the beam port are horizontally aligned.
7.2.3 If it is necessary to view the object during the irradiation (such as the meter on a survey instrument), focus the closed circuit television camera so that an acceptable picture is visible on the remote television display. Adjust remote display so that it is conveniently visible from behind the source.
7.2.4 Withdraw required attenuators for the dose rate desired.
7.2.5 If a timed, integrated exposure is to be used, push the button at the rear of the source to reveal the thumb wheels.
Set the desired time in minutes by dialing in the appropriate numbers.
Mhen the source rod is raised, the exposure will begin.
The timer will then teminate the exposure at the end of the pre-set interval.
7.2.6 For suvey instrument calibiation, the source is cperated manually for a desired dose rate. After exposing the instrument and observing the response, adjustments are often l
made on the instrument.
Before stepping in front of the source, lower source rod, insert all attenuators and verify source is still not exposed.
7.2.7 After completion of the irradiation, lower. the source rod and replace the attenuators. Secure source by removing the key from the calibrator and locking the padlock on the source rod to prevent it from being raised.
7.2.8 Lock the room and return the keys to their proper location.
8.0 REPORTING
' 8.1 Report andy deficiencies or unusual results to the. manager.
N1-3
' ATTACIDIENT # 7 (Con,t ' d) I 25JAN85.NRC
- (Page 43 0F 8,8)
(PAGE I16 OF 169) i Decemb[rf 19[8 Procedure No. N1 8.2 Report any possible exposure to individuals or any problems with the source or alann system operation to the Radiation Safety Officer.
9.0 RECORDING 9.1 Record the required information on the source utilization log.
10.0 ATTACHMENTS 10.1 RMC Source Utilization Log.
Use of RMC Source #53.
10.2 RMC Authorized Source User and Approval Form.
)
I I
9 r *-
N1-4
- + <,, - -
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.-,,w,
,-.y-
-.-y-g y
ATTACllMENT #7(Con t 'd).(\\~/
T
'JCENSENo. 37-13129-01
<R25JAN85.NRC (Fage 44 OF 88)
(PAGE 117 0F 169)
?
F3
/42
-RMC SOURCE UTILIZATION LOG USE OF RMC SOURCE #53 BATE USER
-00SIMETER DATA
- KEY INITIAL FINAL NET RETURNED **
i
- Place a check mark in the " NET" column if a regularly assigned TLD is worn.
If no assigned TLD is ' worn, record the initial, final and net pockat. dosimeter readings in the appropriate columns.
- Place a check mark in the " KEY RETURNED" column to signify the keys are returned.
I N1-5
ATTACID1ENT # 7 (Con t ' d) C'T (PAGE 118 0F 169) ['
, December, 1978 RR25JAN85.NRC V
(Page 45 0F 8,8')
7 74
/yy
, Procedure No. N1 RC AUDORIZED SOUPG WER AND APPIOVAL E021 Procedure Familiarity (User's initials and date)
User
(
Procedure R-9 Procedure R-15 Approval O
e 9
P
(
t N1-6
ATTACHMENT #7(Cont'd) fjCENSENO. 37-13129-01 (Page 46 0F 86) ut25JAN83.NRC (PAGE 119 0F 169).
'i
'12
/ 4.?
Procedure No. N2 l
P,ev. 2 June,1982 CALIBRATION OF RADIATION SURVEY INSTRUMENTS W
z.
Approved by:
~-
DATE INITIALS REVISIONS Rev. No.
Date Para Page Approved by Date
~
1 2/80 7.1.1 2/20/80 1
2/80 Delete 2/20/80 9.2.4 1
2/80 Delete 2/20/80 10.3 2
6/82 Revised Revised l
l
(3 n,c u t no. > < - t 31.f v-01 ATTACIDIENT il7(Cont 'd) V viR25JAN85.NRC (Page 47 0F SS)
(PAGE 120 0F 169) 7 Procedure N2
?S' /1 )
~
Revision 2 June, 1982 CALIBRATION OF RADIATION SURVEY INSTRUMENTS 1.0 PURPOSE This procedure provides instructions for calibration of' radiation survey instruments, according to the manufacturer's instructions, Regulatory Guides, and appropriate ANSI standards, and assures that proper radiation safety methods are used.
2.0 SCOPE This procedure is limited to the safe and proper methods for calibration of radiation survey instruments.
3.0 DEFINITIONS As used in this procedure:
3.1 Radiation Survey Instrument (or meter):
a device, usually portable,
~
used to quantitatively measure radiation.
3.2 "Attenuator" means the devices used to reduce the radiation beam intensity to convenient levels as necessary. Each attenuator is denoted by its nominal reduction factor (e.g. the X 100 attenuator refers to that attenuator'which reduces the intensity of the radiation beam by a factor of approximately 100). NOTE: The actual value of each attenuator is a known value.
3.3
" Center of Detection" means that point within the detector chamber l
that sees the average radiation level seen by the detector. This is normally very near the mechanical center of the detector volume.
4.0 REFERENCES
i 4.1 Radiation Protection Procedures, RMC Procedure R-9.
4.2 Operating manual for Series 28 Calibration Facitities, J. L.
Sheppard and Associates.
4.3 Exposure rate data for Series 28, serial 'humber 603 irradiator.
This is a table of source output versus distance from source and l
attenuator used.
~
4.4 Certificates of calibrations for all radiation sources,. pulsers and other instruments used.
N2-1 l
'NIGNSE NU. 37-1312'3-01 ATTACHMENT #7(Cont'd)
R2SJAN85.NRC (Page 48 0F 88)
(PACE 121 0F 169)
{
N Proce$u'reNI#)
\\
Revision 2 June,1982 1
4.S Abstracts of instrument manufactures technical manuals and/or RMC procedures describing the actual calibration method for each specific survey instrument.
4.6 Use of Cs-137 Gamma Calibrator (RMC procedure N1).
4.7 Ouality Assurance Program for Survey instrument Calibration and Repair.
4.8 Reculatory Guides:
- 4. 8.1 RG 8.4, " Direct-Reading and Indirect-Reading Pocket Dosimeters",(. References-ANSI.N13.5-1972).
4.8.2 RG 8.21, Heal.th Physics Surveys for Byproduct Material at NRC - Licensed processing and Manufacturing Plants; paragraph 1.12, Calibration of Radiation Safety Instruments.
4.8.3 RG 8.23, " Radiation Safety Surveys-at Medical Institutions:", paragraph.1.12 Calibration and Source Checks of Radiation Safety Instruments.
4.8.4 RG 8.24, "Healtri P5ysics Surveys During Enriched Urantum-235 Processing and fuel Fahrtcation",
paragraphl.11, Calibration of Radiation S'afety-I:nstruments.
4.8.5 RG 10.2, " Guidance to Academic Institutions Applying for Specific 8yproduct Material Licenses of~ Limited Scope".
4.8.6 RG 10.3, " Guide for the Preparation of Applications for Special Nuclear Material Licenses of Less than Critical Mass Quantities".
4.8.7 RG 10.5, " Applications for Type A Licenses of Broad Scope".
4.8.8 RG 10.6, " Guide for the Preparation of Applications for Use of Sealed Sources and Deyices for Performing Industrial Radiography".
4.8.9 RG 10.7, " Guide for the Preparation of Applications for Licenses for Laboratory Use of Small Quanti. ties of Byproduct.Naterial".
N2-2
-ATTAC10!EST #7(Cont'd) kRb5JbF5.NRb 3
(Page 49 0F 8E)
(PAGE 122 0F 169)
Procedure N2 jo g
Revision 2 June,1982 4.8.30 RG 10.8, " Guide for the. Preparation of Applications for Medi. cal Programs".
4.9 ANSI Standards ANSI N13.4-1971, "American National Standard for the Specification of Portable X-or Gamma Radiation Survey Instruments".
ANSI N13.5-1972, "American National Standard Performance Specifications for Direct Reading and Indirect Reading Pocket Dosimeters for X-and Gamma Radiation".
ANSI N323-1978, "American National Standard Radiation Protection Instrumentation Test and Calibration".
5.0
-SAFETY PRECAUTI.ONS 5.1 Only authorized users may use calibration sources at RMC Technical Services.
5.2 liear. assigned personal TLD Badge when using any of the calibration sources.
4 5.3 Avoid electrical shock hazards and instrument damage by turning survey instrument off before opening the case.
6.0 APPARATUS 6.1 Calibrationsource(s).
6,2 Small screwdriver for adjusting calibration potentiometers.
6.3 Closed circuit television system.
7.Q INSTRUCTI.ONS 7.1 Preliminary Instructions
'7.1.1.
All shipments of survey instruments should be accompanied by an " inventory sheet" specifying; client, date of shipment, purchase orden number, type of instrument (s), model number (s), serial number (~s), and
.a comment describing reason for calibration / repair.
If this information is not forwarded by client, it should be received,before you begin any calibration or repair work.
N2-3
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LICENSENO.37-131 01 ATTACID1ENT #7(cont'd)~
RR25JAN85.NRC (Page 50 0F 88)
(PAGE 123 OF 169) l
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/U Procedure N2 Revision 2 June, 1982 7.1.2 Assign each instrument an unique RNC identiff. cation number.
7.1.3 Prepare a Instrument Maintenance and Calibration Sheet for each instrument. This form accompanies the instrument throughout its calibration or repair.
Pull the Instrument Calibration and Maintenance file folder from the file or prepare a new one if it is a new instrument.
7.1.4 Acknowledge receipt of instruments shipped to RMC from outside our local service area (Delaware Valley) and/or for all instruments received for repair.
7.1.5 Inspect the instrument for damages or deficiencies.
Write the observations on the remarks section of the Calibration Data Sheet.
7.1. 6 Change batteries in the instrument.
7.1.7 Check instrument desicant and replace or recharge if necessary.
7,1.8 Turn the instrument on and allow for a suitable warm up period as specified by the manufacturer's specifica-tions.
7.1.9 Test the sensitivity, high voltage and ratemeter response if indicated.
Record the data on the data sheet.
7.2
' Instructions Proper 7.2.1
. Survey instruments are to be calibrated at two points, separated by at least 50% of each scale that is used routinely for linear readout instruments, and one point per decade'for logarithmetic readout instruments. Choose available dose rates and write these values on the Calibration Data Sheet.
7.2.2 Position the center of detection of the survey instrument so that the output of the radiation source corresponds to one of the calibration points.
Place the detector with care, i 0. 2cm is uslually sufficient.
~
7.2.3 If the Cs-137, irradiator is being used, focus the closed circuit television camera to view the meter of the survey instrument.
Position the video monitor so that it can be viewed from behind the source.
N2-4~
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( N.that hu.-n-13129-01 ATTACllMENT #7(Cont'd) d L h25JAN85.NRC (Page 51 0F 8,8)
(PAGE 124 OF 169)
ProcedufeN2 Revision 2 June, 1982
~7.2.4
-Expose the survey instrument to the radiation and record the response in the "BEFORE CALIBRATION" column of the Calibration Data Sheet. Do not adjust instrument yet.
-7.2.5 Repeat steps 7.2.2 and 7.2.4 for all of the calibration points. NOTE:
It is important to note the before i
calibration response of the instrument. This infoma-tion is very important to the client if the instrument
. is badly out of calibration or for any instrument that may need repair.
7.2.6 If the response of the survey instrument is acceptable, record this as the final reading.
If it is not acceptable, refer to the specific calibration method for this instru-ment for instructions for adjustment.
Follow these adjustment instructions for each of the predetemined calibration points until either a valid calibration is obtained or it is detemined that the instrument cannot be calibrated. Adjust the readings as required by the manufacturer's instructions to compensate for tempera-ture and pressure and. energy dependence.
7.2.7 A valid calibration is complete if all instrument readings are within 110% (or the manufacturer's accuracy specifications if greater than.10%) of the known radiation values. Readings within 20% are acceptable if a calibra-tion chart ce graph is prepared and made available with the instrument. NOTE: Some clients may require a stricter tolerance for acceptable calibrations.
i 7.2.8 Write in the required infomation on the Calibration Data Sheet as the work is perfomed.
4 7.2.9 Replace the old calibration sticker with an updated one.
7.2.10 If a valid calibration cannot be obtained, tag the instru-i ment for repair' and write in the symptoms on the Calibration Data Sheet.
7.2.11 For Quality Assurance, 2% or more of all instruments shall be recalibrated by another individual. Record the results of the QC calibration on a separate calibration sheet and record the QC te'st result in the Calibration Lab logbook.
Any discrepancies will be noted and resolved by the Supervisor, Indtrument Calibration.
1 N2-5
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25JkN85.NRb ATTACHMEST #7(Cont'd)
(Page520Fgg)
(PAGE 125 0F 169) y
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Procedure N2 Revision 2 June,1982 7.3
'Special Calibrations From time to time clients may require calibration procedures that are not as specified by the manufacturer or this procedure.
In this case, a special calibrati'on procedure shall be prepared and followed.
Special calibration procedures shall be in writing and shall.be approved by the Manager of the Calibration facili ty.
8.0 REPORTING 8.' 1 Prepare a calibration certificate showing the results of the calibration.
Place a copy of this certificate in the instrument file and send the~ original to the cl' 8.2 As a minimum, each instrument returned to a ci after calibration and/or repair shall have:
8.2.1 A valid calibration sticker placed on the instrument.
8.2.2 A Calibrati'on Certificate.
8.3 Report the results of all QC tests to the DQAC on a monthly basis.
8.4 Prepare a Calibration Due Remi~nder card and send it to the client during the last week of the month preceeding the calibration due month.
8.5 Pack an 00T OF CALIBRATION tag with the instrument for use By the client.
9.0 RECORDS 9.1 The individual performing the calibration of survey instruments is responsible for completing all data sheets completely and accurately. The supervisor signifies his approval of data l
sheets by signing in the space provided.
9.2 Calibration data and repair forms are retained for two years by instrument make, model and serial number.
N2-6
ATTACHMENT #7(Cont'd) jg5]{38 hRC 7
(Page 53 0F 88)
(PAGE 126 0F 169)
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Procedure N6 Revision 2 June, 1982 10.0 ATTACHMENTS 10.1 Instrument Calibration and Maintenance Record.
10.2 Instrument Maintenance and Calibration / Instrument Service-Repair form
.10.3 Certificate of-Calibration 10.4 Calibration sticker 10.5 Battery Change sticker
+
10.6 Repatr.and Calibration Acknowledgerent 10.7 Out of Calibration tag 10.8 RMC Reminder: Calibration Due I
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[ ] CESSE No. 37-13129-01 ATTACllMENT #7(Cont 'd) U L A25JAN8$.NRC (PageSSOF8f)
(PAGE 128 0F 169) j lM
/43 radiation management corporation INSTRUMENT
$NEET or gagggi-MAINTENANCE
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CALIBRATION 8'
Instrument ID Inst. Model:
SN:
MFGR:
Probe Model:
IN:
Owner BILLING ADDRESS:
NAME:
ADDRESS:
STREET:
Person to
Contact:
Phone:
CITY:
STATE:
ZIP:
INSTRUMENT CHECK BEFORE ADJUSTMENT Visual OK 25% FULL SCALE 75% FULL SCALE Insoection O RANGE Pulser Readino-Pulser Rea dine COMMENT Battery LK Chance U
Normal LK Operation U
Sensitivity OK Pulse mv O High Volts (K
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Total O BILLABLE D NON.81LLABLE O WARRANTY O SERVICE CONTRACT Work Done By:
Date:
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Date:
Supervisor:
Date:
Totvard to Contracts for billing. After invoicing return to Calib. shop Tiles.
10.2 Instrument Maintenance and Calibration /
Instrument Service--Repair Fonn (Front)
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INSTRUMENT SERVICE - REP AIR a
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Radiation Management Corporation certmos that the instrument Ileted tmlow v... estibreted and in;peced rt 8
before shipment and has met the manufacturet's published specifications. RMC certmos that our cattbration
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CALIBRATION SOURCE ID-I RMC 8ERVICE NO.-
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Calibration I certify that the above Information le correct.
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Authortaed Agent hn Date Thle Data en ' :.
j (RMC not toeponobio for demeGe locurred during ahlpment or use of mio instrumenQ 4
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OUT OF CALIBRATION O
00 uor use FOR CALIBRATION SERVICE SEND TO: '
RMC - 3508 MARKET ST., PHILA. PA 19104 (215) 243-2950 ATTN: CALIBRATION LAB N.
INST.10.
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REPAIR & Call 8 RAT 10N ACKNOWLEDGEME J/o
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Dear Customer:
m te) and have been assigned our CONTROL NO. as showrt If this schedule cannot be met, we Retum shipment is scheduled for will call you and let you know.
INSTRUMENT MODEL NO.
SERIAL NO.
RMC CONTROL NO.
If you have any questions about this repair order, please call us at (215) 243 2950.
Ref. your P.O.*
Instrument Repair & Calibration Service Coordinator or Ref.*
, RMC-TECHNICAL SERYlCES 350s Manet St., P.O. sont 7940. PhiladelPhla PA 19101215-243 2950 RMC-TECHNICAL SERVICES POSTAGE 3508 MARKET STREET PHILADELPHIA, PA 19101 RETURN POSTAGE GUARANTEED TO:
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DEPARTMENT:
ATTEN'10N:
10.6 Repair and Calibration Acknowledgement I
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RMC REMlN DER: CAL lBRATION DUE!
YOUR INSTRUMENT MAKE MODEL SN IS OUE FOR CAllBRATION ON DATE SEND IT WITH YOUR PURCHASE ORDER NUMBER TO:
RMC CAllBRATION SERVICES 3508 MARKET STREET PHILADELPHIA, PA 19104 72 HOUR SHOP TIME GUARANTEED FOR STANDARD CAllBRATION 10.8 RMC Reminder:
Calibration Due e
E No. 37-131/701 ATTACH.9ENT // 7 (Con t ' d)
RR25JAN85.NRC U
(Page 61 OF 8,8')
(PAGE 134 0F 169) i Decenter, 1978 gg g7 Procedure No. N3 Rev. 2 June. 1980 REPAIR OF RADIATIOf( SURVEY INSTRUMENTS I-l f
- - J ' - 8*
Approved by-A Date Initials Fred G. Rocco Vice President. Technical Services REVISIONS Rev. No.
Date Para.
P3
@ roved by Date_
1 2/80 7.1. 3 T17-2 1
2/80 10.1 T17-3 4
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l 2
6/80 7.1.3.,& 10.1 T17-2 & 3
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Im My August 1978 Procedure No. N3 REPAIR OF RADIATION SURVEY INSTRUMENTS 1.0 PURPOSE The purpose of this procedure is to provide the-necessary instructions for the repair of radiation survey instruments.
2.0 SCOPE This procedure applies only to the repair of radiation survey instruments and not to their calibration.
Since the repair of each survey instrument is likely to be quite different from others, this document describes a general repair procedure. Specific references are to be used as needed.
3.0 DEFINITIONS As used in this procedure:
3.1 - Radiation Survey Instrunent (or meter) - A device, usually portable,.
used to quantitatively measure radiation.
4.0 REFERENCES
4.1 Calibration of radiction survey instruments (RMC Procedure T-16).
4.2 Abstracts of manufacturer s technical manuals. describing the testing 3
and repair methods for each specific survey instrument.
4.3 Instruction manuals for test equipment that ray be necessary for repair of certain instruments.
5.0-SAFETY PRECAUTIONS 5.1 Observe any electrical safety precautions to prevent electrical shocks or damage to. equiprent.
6.0 APPARATUS 6.1 Survey instrument to be repaired.
6.2 Miscellaneous repair tools (e.g. screwdriver, soldering iron, etc.).
6.3 Miscellaneous test equipment as needed (e.g. voltmeter, signal generator, etc.).
6.4 Spare parts and batteries as. needed. '
7.0 INSTRUCTIONS 7.1 Preliminary Instructions 7.' 1.1 Fill out the indicated forcs and perform the battery check according to the preliminary instructions in procedure T-16 (Calibration of Radiation Survey Instrunents).
N3-1
g g L t,M t.
AU.
J/-lJ14V-VI ATTACIDiENT #7(Cont'd)
A25JAN85.NRC (Page 63 OF 88) 1
(,PAGE 136 0F 169)
Augus t,19b Procedure 11o. ti3 7.1.2 Prepare an instrument repair order sheet to accorpany each ins trument.
Fill out the indicated spaces.
Rev. 2 7.1.3 Refer to the inventory sheet or to any tags on the instrunent June,'8C for the reason for repair. Record a description of the defect or deficiency in the indicated spaces on the instrument service /
repair sheet.
7.2 Instructions proper 7.2.1 Refer to the manufacturer's techincal manual for the particular survey instrument to be repaired and proceed with the indicated check out method.
7.2.2 After checking the instrument, estimate the cost of repair (parts plus labor).
If the estimated repair costs are gmater than 25% of the cost of replacing with a new instrument, check with the supervisor of instrument repair for approval.
If repr:rs are estimated to be greater than 50% of the cost of nplacing with a new instrument, approval from client shall be obtained prior to commencement of repairs.
7.2.3 Replace parts and pc.rform repair as. per manufacturer's instruc-tions in technical manual. Record information on the parts used and the time spent in checkout and repair on the instrument repair order sheet.
Adjust inventory to reflect any parts used.
7.2.4 All defective or apparently defective parts that are mmoved
- from the instrument should be discarded or tagged to indicate the status of each.
This will pmvent reuse of defective parts.
7.2.5 A cumulative listing of the type and nunber of parts used within the past twelve month period is to be maintained. The nominal parts inventory will ~be between 50% and 100% of this usage.
Modifications to this inventory may be made to consider parts with limited shelf life, patts with a relatively high cost and parts with a relatively low cost.
7.2.6 After an instrunent has been repaired, calibrate the instrument according to Pmcedure T-16.
l10TE: If only the batteries are replaced, calibration is not necessary unless it is due.
7.2.7 If an instrument can not be repaired, check with client to de-termine next course of action.
8.0 REPORTIl1G 8.1 Repaired instruments are to be returned to the standards lab for cali-bration. All required forins should acconpany each instrument.
8.2 All applicable sections of the requimd forms are to be filled out.
After approval by supervisor, instruments and forns are to be trans-j mitted to clients.
N3-2 l
A s t..s a c. aus. J s - l J il')-U l ATTACIDiENT #7(Con,t 'd)-
125JAN85.NRC (Page.64 0F Bf)
(PAGE 137 0F 169)
//5
/42 Augus t, 1978 Procedure No. N3 9.0 RECORDING 9.1 The individual supervising the calibration / repair of survey instruments is responsible for examining all' data shee.ts for completeness and accuracy. The supervisor signifies his approval by signing in the space provided.
9.2 Sufficient copies of forms should be retained for RMC files.
_ 10.0 ATTACHMENTS R:v. 2 10.1 Instrument Service / Repair Sheet.
O 4
9 9
N3-3
ATTACIDIENT #7 (Con.t 'd)
R 5 85 NR 8
(Page 65 0F 88)
(PAGE 138 0F 169)
_7
- //4.
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INSTRUMENT SERVICC/ REPAIR SHEET Customer P.O. R Receipt Date
. Customer
- Equipment type Model R Manufacturer.
Serial I warranty status in C out Description of Defect Corrective Action Dates 6
r Labor Parts Part R Description Qty U/P Total Description Mrs.
.-Rate
. Total Repair-Reg l
i Repair OT Travel Expenses Total Parts Total Labor Parts Bill,ing Status Billable
~
Other Repaired by Completion Date,'
yo 333,yy, Total Reoair 0 Waitanty L
Supervisor Date Q Service Contract f
I N3-4
' - ttttadt 60. J/-13129-ul ATTACilMENT'#7(Cont'd)
R25JAN85.NRC'
-(Page66OF8p)
(PAGE 139 OF 109) b U?
/42 Summary of Procedure for Repair of Survey Instruments 1.
Prepare a service order / repair sheet.
2.
From client data,' describe defect on service order.
3.
Review technical manual.
4.
Estimate repair cost:
Parts, Labor. Client approval required for >50% of replacement ~ cost.
5.
Repair instrument.
Record parts used and labor hours on service order.
6.
Adjust parts' inventory.
7.
Save defective parts and return to client.
8.
Don't reuse old parts.
9.
Keep running 12 month parts use.
- 10. Order inventory to have 50% to 100% of annual use rate.
- 11. Calibrate according to T-16.
12.
If you can't repair, ' check with client.
- 13. Repaired instruments must be calibrated.
- 14. Service order goes~to client with instrument and used parts.
.15.
Supervisor reviews all r6 pair work.
03626
O o
EICENSE NO. 37-13129-01
<TTACIDIENT #7(Cont'd)
RR25JAN85.NRC l(Page 67 0F 88)
(PAGE 140 0F 169)
If2
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Noven6er, 1979 Procedure No. N-5 i
SEALED - SOURCE LEAK TEST PROCEDURE
(%..
J.
I
//-/J M Approved by Nte em,
l Fred G. Rocco Vice President. Technical Services REVISIONS i
_P_a ge_
Aporoved by Date_
I a
Ecy. No.
Date_
Para.
~
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.m.,_
ENSE NO. 37-13129-01 ATTACIDIENT f 7 (Con t ' d)
RR25JAN85.NRC (Page 66 oF M)
(PAGE 141 OF 169)
Hovember.$79
-(,
Procedure No. N-5
(. (.
SEALED - SOURCE LEAK TEST PROCEDURE 1.0 PURPOSE The purpose of this procedure is to provide instructions' for performing a leak test on a sealed source.
2.0 SCOPE This procedure shall apply to any sealed source as defined below and has any of the following properties:
1.' Contains.rore than 100 microceries of a Ntair garraa emitter.
2.
Contains more than 10 microcuries of an alpha emitter.
3.0 DEFINITIONS 3.1 A.seded - source is defined as any radioactive material that is encased in a capsule designed to prevent leakage or escape of the i
radioactive material and is intended for use as a sealed source.
This does not include radioactive material that is encapsulated to prevent leakage or escape of the material when the capsule is intended to be opened and the source used in an unsealed form
(-(.'
during shipment. The ampule in this case is intended to be (e.g., sources (usually'known standard solutions) supplied by vendors are often supplied in sealed ampules for protection opened and the source utilized for tracer work, instrument standardization, etc.).
3.1.1 A small sealed source is defined as any sealed source with an activity of less than 1.0 mci Cobalt-60 or equivalent.
3.1.2 A medium sized sealed source is defined as any sealed source with an activity of greater than or equal to 1.0 mci Cobalt-60 or equivalent and less than or equal to 1.0 Ci Cobalt-60 or equivalent.
3.1.3 A large sealed source is defined as any sealed source with an activity of greater than 1.0 C1 Cobalt-60 or equivalent.
3.1.4 An environmental fluid is defined as any non-solid physical state of matter, specifically gas (e.g. airl or ifquid (e.g. water).
4.0 REFERENCES
4.1 U.S. NRC Regulatory Guide lO.7, " Guide for the Preparation of C(.
Applications for Licenses for Laboratory Use of small Quantities of Byproduct Material". February,1977.
N-5-1
CENSE No. 37-13129-01 ATTACll!!ENT f 7(Cont 'd)
RR25JAN85.NRC (Page 69 0F SJ)
(PAGE 142 CF 169) 12 c,
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November, 1979 Procedure No. N-5 4.2 RitC Procedure R9, " Radiation Protection Pmcedure." Rev.1 November, 1979.
4.3 Radiation fianagement Corporation's Application for Byproduct P.aterial License (Industrial), Fom NRC -313 I (6-78) 10 CFR 30 License Number 37-13129-01.
5.0 PRECAUTIONS All precautions required for the safe handling of radioactive materials should be followed as per reference 4.2.
In'all_ cases, the'ALARA phil-osophy will be followed when leak testing a sealed source. Use tweezers or tongs where practicable to avoid direct handling of any sealed source.
5.1' Specific precautions 5.1.1 When leak testing a small sealed source plastic gloves nust be worn. A small sealed source may be leak tested by direct wiping or smearing, whenever practical. If small sealed sources are permanently installed in a device, the closest opening or aperature will be wiped or smeared. If the source may be damaged or modified by direct wiping or smearing, then the closest accessible surface will be wiped or smeared.
5.1.2 When leak testing a medium sized sealed source, plastic gloves must be worn. A medium sized sealed source may be leak tested by direct wiping or smearing if the process is not likely to expose personnel. If medium sized sealed sources are permanen-
' tly installed in a device, the closest opening or aperature will be wiped or smeared.
If the source may be damaged or nodified by direct wiping or smearing, then the' closest accessible surface will be wiped or smeared.
5.1.3 When leak testing a large sealed source, plastic gloves must be worn. Direct wiping or smearing of a large sealed source by persennel will never take place. Wiping or smearing of a large sealed source will only take place in a hot cell or a similar remote manipulating device. Large sealed sources will not be dismantled to perform a leak test. The closest opening, aperature or shutter will be wiped or smeared enless there is a reasonable way of sampling environmental fluids.
If the sealed source may be damaged or modified by direct wiping or smearing, then the closest accessible surface will be wiped or sme:..ad.
5.1.4 If any sealed source is moved'by or stored in an environmental fluid, then this fluid shall be sampled and analyzed to detect possible sealed source leskage.
6.1 Smears or Wipes NS-2
ESSE No. 37-13129-01 ATTACl! MENT #7(Cont'd)
RR25JAN85.SRC (Page 70 0F 86)
(PAGE 143 0F 169)
}%/
/42 November, 1979 Procedure No. N-5 6.2 Appropriate analytical equipment for the specific sample and type of radiation needing analysis.
6.3 Tongs, tweezers or other remote handling devices as appropriate.
7.0 INSTRUCTIONS i
'1 The qualifications of personnel who will perfom or directly super-vise th6 leak testing are included as attachments 1 and 2 of Item-
~
6 and 7 of reference 4.3.
7.2 A listing of the radiation detection i s.truments and radioactivity,
!1 measurements instrumentation used for assay of test samples are included as attachment 5 of Item 10 and attachment 7 of Item 13 of reference 4.3.
Radiation detection instrumentation to be used must be capable of detec ting the presence of 0.005 microcuries of radioactive material on the test sanple.
7.3 Instrument calibration procedures for radiation detection instru-ments are included as attachment 6 of Item 11 of reference 4.3.
Calibration of radioactivity measurements instrumentation is performed as follows:
7.3.1 For the gas-flow proportional counters an NBS traceable
(.(
Sr-Y-90 or Pu-239 check source of known activity is used to determine the beta and alpha counting efficiencies respectively at a minimum of at least once a week but usually every working day.
7.3.2 For the liquid scintillation counters an NBS traceable source of tritiated water of a known activity is added.
to sufficient distilled water to obtain a sample in the standard geometry, sealed and counted at least once a week and usually 4 or 5 times a week to determine the counter efficiency.
7.3.3 For the ganma spectroscopy system, an NBS traceable mixed source is used to determine the efficiency over the entire range of the energy spectrum annually. The counting efficiency is checked on a weekly basis using a multi-energy source.
7.4 The individual (s) as specified in 6.1 following the safety pmcedures in 5.0, shall perform a leak test as follows:
7.4.1 If the source is used outside of its shielded container, it shall be removed from its shielded container and the centainer shall be swiped and the removable contamination measured.
(,,
\\
7.4.2 If a source is used in a shielded tainer, the container shall be swiped, the container sha)I be swiped at locations most likely to become contaminated by a leaking source.
7.5 The material used to take the leak test shall be counted on the appmpriate instrumentation and the results calculated.
NS-3
ENSE NO.37-131'9-01 ATTACHMENT li7(Cont'd)
RR25JAN85.NRC (Page'71 0F 86).
(PAGE 144 0F 169)
/22
/4) f.
November, 1979
((
Procedure No. N-S' 7.6 The calculations will be perforraed using the general equation:
Resul t (uCi/ sample) = ((S/T) - (B/t)) / (2.22 x 106 E) where:
.S Gross counts of the sample
=
B = -Counts of the clank 4
E Fractional ' counting efficiency
=
T Number of minutes the sample was counted
=
2.22 x 1ger of minutes the blank was counted t
Nu
=
0 converts dpm to microcuries 8.0 RECORDS A record of all leak tests performed including the date performed will be recorded and kept on file.
9.0 REPORTING 9.1 Leak test results shall be reviewed and signed or initialed by the RSO or his designate.
9.2 If the test reveals the presence of 0.005-microcuries ~or more of removable contamination, the source shall be imediately withdrawn C(.,
applicable regulations. A report shall be filed within 5 days of from use and~ decontaminated, repaired-or dispos'ed of according to the test to the USNRC regional office describing the equipment involved, the test results and the corrective action taken.
9 9
i' D
f(.
NS-4
O O
Procedure ilo. ill2 LICENSE No. 37-13129-01 ATTACID1ENT f/7 f Cont'd) '
.Rev. O, Aug, 9, 1983 RR25JAN85.NRC (Page 72 OF 83')
(PAGE 145 OF 169) 173
/4 )
e GENERAL PROCEDURE FOR PERFORMING RADIOLOGICAL SURVEYS Approved by Date Initials RECORD OF REVISIONS 4
Rev. No.
Dge_
Page Approved by Date 0
,8/9/83
- *
- Original issue * *
- N12-1 i
i CENSE NO. 37-13129-01 ATTACID1ENT #7(Cont'd)
RR25JAN85.NRC 2
(Page'73 0F 88)
(PAGE 146 OF 169)
/29
/4 )
GENERAL PROCEDURE FOR PERFORMING RADIOLOGICAL SURVEYS
~
1.0
. PURPOSE The purpose of this procedure is to outline those radiological survey methods to be used to determine the extent of contamination (or lack of it) at a site, or sites, of interest; to provide health physics support data on personnel-and equipment; and/or to determine that levels of activ.ity meet those designated for unrestricted use of an area or facility.
2.0 SCOPE This procedure applies to all RMC personnel whose assigned task shall be to provide radiological and/or health physics support, by-means of radiological surveys.
3.0 REFERENCES
3.1 RMC PROCEDURE NO. MQ6; TRAINING AND CERTIFICATION OF INDIVIDUALS RESPONSIBLE FOR RADIOLOGICAL MEASUREMENTS.
3.2 - REGULATORY GUIDE 8.21; HEALTH PHYSICS SURVEYS FOR BYPRODUCT MATERIAL AT NRC LICENSED PROCESSING AND MANUFACTURING PLANTS.
3.3 USNRC RULES AND REGULATIONS, TITLE 10, PART 20, APPENDIX B.
TABLE II, Column 1.
3.4 RMC PROCEDURE NO. MR2; THE MAINTENANCE AND CALIBRATION OF RADIATION SURVEY INSTRUMENTS.
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1
(
CENSE No. 37-13129-01 ATTACIDIENT I!7(Cont 'd)
RR25JAN85.NRC (Page 74 0F 88)
(PAGE 147 0F 169)
/2,5
/17 3.5 USNRC, ORAFT, GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OF TERMINATION OF LICENSEES FOR BYPRODUCT, SOURCE, OR SPECIAL NUCLEAR MATERIAL.
4.0 PROCEDURE Radiological surveys performed shall include those necessary to evaluate -
environmental and personnel studies. They shall be conducted to determine
~
levels of airborne concentration, and levels of surface contamination on equipment, protective clothing, etc., and the extent of contamination (if any) in an area of interest. Those persons responsible for making radiological surveys shall be trained and certified as per reference 3.1.
14.1 Air Samples 4.1.1 Environmental Samples a) High or low volume air samples shall be taken at
. locations upwind and downwind of the area of interest to verify the presence or absence of airborne contaminants.
b) These samples shall be taken on the initial site visit and at routine intervals throughout the radiation survey period.
c) The procedure for taking these air samples is given in Appendix I.
4.1.2 Breathing Zone Samples a) These samples shall be representative of the air in the worker's breathing zone.
b) These samples shall be taken while site work (if any) is in progress, either 'on a continuous basis or dt e
2
ICENSE NO. 37-13129-01 ATTACHMENT'#7(Cont'd)'
-RR25JAN85.NRC-(Page 75 CF 88) '
(PAGE 148 0F 169) 12 4
/D routine intervals if cortinuous monitoring is deemed impractical or unnecessary, c) The procedure for taking these samples is the same as for low volume-air samples, Section 4.1.1.
This procedure is given in Appendix I.
4.2 Surface Contamination- (Ref. 3.2) t-Area surveys shall be conducted as soon as practicable after.
arriving at the site of interest. Subsequent area surveys shall be made routinely or as deemed necessary throughout the project undertaken.
4.2.1 Surface containination surveys shall be conducted to determine 3;
the presence and/or extent of contamination, both fixed and i-removable,- on surfaces such as:
a) the surfac'e of the involved equipment b) the surface of involved vehicles c) road and ground surfaces around the site of interest d) protective clothing of work personnel e) when applicable, skin surfaces of personnel and work crews f) the procedure for performing surface contamination surveys is given in Appendix II-A.
4.2.2 Removable Surface Contamination Survey Smear senpling is a means for the determination of removable surface contamination. Smear samples can be performed on those areas listed in Section 4.2.1.
0 0
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(
ENSE No.' 37-11129-01 ATTACIDIENT #7(Cont'd)
' RR25JAN85.NRC
.(Page 76 0F 8;S')
(PAGE 149 0F 169)
'l
/zs
/g7 a) The procedure for performing smear surveys' is given in Appendix 11-8.
5.0 REPORTS 5.1 All data obtained during radiation surveys shall be noted..in legible form, on the supplied appropriate surveys forms. The technic'ian/HP
-performing the survey shall initial or sign the survey form.
5.2 All collected data shall be given to the Senior HP or his supervisor
~
for his/her review and approval.
6.0 RECORDS All records formulated /obtained from radiological surveys shall be retained as specified in Reference 3.2.
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(_, TENSE!;0. 37-13129-01 ATTACllMENT #7(Cont'd)
RR25JA:85.NRC f
(Page 77 0F 8))
(PAGE 150 0F 169) i Appendix I 9
/2 &
N' AIR SAMPLES 1.0 Taking the ample:
1.1 If a high volume sampler is used; a) prepare the sampier/ filter as described in the appropriate in-struction manual.
b) representative sites, upwind and downwind of the site of interest, shall be selected and noted in the field log and on an area map / diagram.
c) the following information shall be recorded on the appropriate survey form (Attachment I):
- 1) duration of sample in minutes 2) instrument flow rate
- 3) date, time and name of person taking sample d) the sample time shall be sufficient to insure that MPC's (Ref. 3.2) can be seen.
In the case of high volume samples (using the 11cm filters), a minimum total volume of 2800 liters is required.
(This is based on a 4 minute count time and an assumed background of I count per minute /an M)L of 8 DPM).
e) At the end of sampling, remove the filter paper and place it in a holder / envelope in such a manner that it is not disturbed er cross contaminated.
1.2 If a Low Volume Sampler is used:
a) prepare the sampler / filter as described in the appropriate instruction manual.
b) representative sites, upwind and downwind of the site, shall be selected and noted in' the field log and on an area map / diagram.
1-1
CENSE NO. 37-13129-01 ATTACHMENT #7(Cont'd) '
KR25JAN85.NRC (Page 78 0F 8,S)
(PAGE[15'l0F169)
/27 c) The following information shall be recorded on the approp/$t")
riate survey form (Attachment 1):
- 1) duration of sample in minutes
- 2) sampler flow rate
- 3) date, time and name of person taking sample
.d) The sample time shall be sufficient to insure that MpC's (reference 3.2 can be seen. When using a low volume sampler (havin5 a Scm filter) a minimum total volume of 700 liters is required.
(This is based on the same parameters as in Section 1.1-d).
e) At the end of sampling, remove the filter paper and place it
/
in a holder / envelope in such a manner as to not disturb or cross contaminate it.
2.0 Counting the samples:
a)
Set up appropriate instrumentation for making a counts, as specified in applicable instruments operating instructions.
b)
Log date, time, duration, location and name of person taking sample.
c)
Record all counting data and sample information (section "b" above) on appropriate sur'ey form (Attachment 1).
v d)
Prepare the filter for counting.
If the sample was taken using a 5 cm filter, the whole filter is placed on the sample holder tray and counted. The active area observed has a 4.5 cm diam.
If the sample was taken using an 11 cm filter, whose active area has a diameter of 9 cm, a disc of s 4.5 cm diame,ter must be cut out of the filter to be counted. The total volume observed is then corrected by a factor of approximately 0.25.
For example, 2800 liters is sampled through an 11 cm filter. A 4.5 cm (diameter) disc is then removed from the filter in preparation for counting.
1-2
ENSE No. 37-13129-01 ATTACle!ENT #7(Cont'd)
. !!R253AN85.NRC 3
(Page 7.9 0F 88)
(PAGE 152 OF.169) 1
/J o
/p >
The observed volume is calculated as follows: 2800 liters x
-(active area of disc,16cm )
2 4
(active area of filter, 64cm ) or/ 28001 x ~.25 = 700 liters.
2 Care must be taken when holding the filters, to insure that the
{
sample is not disturbed or cross contaminated.
Setting the timer to the desired count time (minimum count time e.
used is 4 minutes), the counts are started.
f.
On completion, the total counts observed and the length of the count are noted on the survey form.
g.
Replace the sample in its holder and store for possible future re-analysis.
Note: Previous to counting samples, background counts shall be i
made to determine the' instruments minimum detectable limits (MDL) and for use in the c.alculations of observed activity.
+;
3'. 0 Calculations:
3.1 Calculating the MOL 1
i The minimum detectable level is. defined as the activity or concentration that will always be detected with only a 5% chance that the activity will be said to be within the background range of the instrumentation or that the background of the instrument will be said to be sample activity.
MDL count rate is given by:
(Total counts, background)1/2 CPM (MDL) 2 1*96 - 2
=
(Total count time, background)
CPM (MOL).
- N(MDL)
E (1-b) fsa where:
E instrument counting efficiency in CPM /DPM
=
b backscatter fraction.
=
0 for alpha; 0.67 for beta with ss planchet
=
f typical correction factor for self absorption in
=
sa the sample 1.0 for 6 eta;
=
For alpha the f and air samples, may'be taken to be 1.30 for smears 3
t i
1-3
-ATTACHMENT #7(Cont'd)-h-
{dSJA::85.SRC TENSE No. 37-13129-01 tu (Page 80 0F 8p) l (PAGE 153 0F 169)
IIE) uCi
=
6 2.22 x 10 uCi/ Dis 3.2 Calculating Observed Activity Total Observed Counts Net CPli
- bk9
=
Total Count Time where bkg = backgmund count rate in' CPM.
flet CPit DPM-
=
E (1-b) fsa where f
= may be taken to be 1.30 or may be estimated as b
~
sa Cu where C is the net count rate of the sample when c covered by another uncontaminated filter paper and C is the net count rate of the
~
u sample when ccunted upside down.
DPM uCi
=
6 2.22 x 10 pCi/DPM uCi uCi for long lived nuclides
=
Sample volume x fy whare f
-is-the-fraction of the sample volume used for the analysis.
y Sample volume is given by:
Vol = G x Flow Rate (start) + Flow Rate (stop) x duration of sample in min' tes
~
u z
where G is' the units correction factor if flow rate'is in G equals 4
CFM 2.832 g 10 LPM 10J -
3 4
M /hr 1.6667 x 10 GFM 472 I-4
/
ENSE No. 37-13129-01 ATTAC10!ENT #7(Cont'd) i RR25JAN85.NRC (Page 81 0F 8p)
(PAGE 154 0F 169)
Appendix II
/3 2-
/47 SURFACE CONTAMINATION 7
General area surveys, to locate and/or ' isolate areas of_ gross contamination.,
l can be made using two different methods; either by surface contanination f
surveys or removable contamination surveys (referred to as smear surveys) or
. both.
Appendix II-A describes the surface contamination survey. Appendix II-B j
. describes the smear survey.
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O 37-13129-01 1825JANSS.NRC (Pace 82 0F 5 4 5 'i (PAGE 155 0F 169) 133 14 ).
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. Page'83 0F.8,8) q
-(PACE 156 0F 169)
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Appendix II-A SURFACE CONTAMINATION SURVEYS i
1.0
. Performing the survey:
4 a) Assemble the appropriate' instrumentation, i.e., end window GM probe, or u scintillation probe, with its associated rate meter and digital scaler, or the low energy PG-1 probe and PAC meter. The instruments shall be checked for proper function and operation. (See Reference 3.4) f b) Background counts are made, in an area free of contamination. The a
background readings are recorded in the Survey Log and on the appro.
priate survey form (Attachment 1).
i.
c) The areas to be surveyed shall be entered into the Survey Log and designated on an area map / diagram.
It may be desirable to grid off 4
the area prior to the survey, for easy reference.
7 d) The survey is perfomed by positioling the probe approximately 1 f
centimeter from the surface of interest, if the GM probe is used,
'or directly on the surface, if the a probe.is used. Care must be j
taken to insure that the face of the probe is not damaged or contaminated.
j.
e) The survey readings shall be of sufficient time to insure that an
{-
accurate, average counts per minute reading or the total observed counts from the scaler (depending on instrumentation used) give results yielding ' good counting statistics. All results are recorded on the appropriate survey form (See Attachment 1).
2.0
. Calculating the results:
~
2.1 If instrumentation having a rate meter, reading in units of average counts per minute is used,,the results are calculated as follows:
a) Average Counts Per Min,te (observed) - Background C.P.M. =
net observed counts per minute.
II-A-1
h 6
A V
CtENSENO. 37-13129-01 ATTACIDIENT 17(Cont'd) '
RR25JAN85.NRC
-(Page840F8f)
(PAGE 157 0F 169) l3.5. /1 )
~"*
I Disintigrations Per Minute
=
.(instruments counting efficiency) 2
= DWcm 6.67cm3 (active area of the prob'e)*
2 DPM/cm -x 100cm2 2
= DPM/100cm
~)
The net' readings are entered on the survey form.
b c) - These net readings are used to denote areas greater than back-ground, or areas of contamination.
2.2 If instrumentation with a scaler is used, the results are calculated '
as follows:
- }
(total observed counts) - (total counts bkgd)
(
total count time
)
(total count time bkgd " "'
net Disintigrations Per Minute
=
(instruments counting efficiency) 2
= WM/cm
- 6.
cm' (activeareaoftheprobe)*
2 2
DPM/cm x 100cm 2
DPM/100cm
=
b) These results shall be entered on the appropriate forms.
The active area of the probe, shown above, is for a Johnson GP-200 end window
.GM probe.
If another probe is used, its active surface area must be calculated.
3.0 Action Levels 3.1 _ If the calculated activity levels are less than or equal to 5000 2
2 DPM/100cm, average, and/or 15,000 DPM/100cm, maximum,- for a and 8-y (see Reference 3.5). the observed area can be considered clean and an attempt should be made to protect it from cross contamination.
3.2-If the calculated activity levels are greater than those listed in Section 3.1, the area is considered contaminated above acceptable levels.
Such areas need continued decontamination efforts.
II-A-2
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/ ^N (N, CENSE NO. 37-13129-01
,,, CH':ENT v,7(Cont,d) ( j
.u i A KR25JAN85.NRC (h'e A 5 0 F ?M e *.'
(PAGE 158 0F 169)
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!!R25JANSS.NRC (Page 86 0F 88)
(PAGE 159 0F 169)
Appendix II-B Si4 EAR SURVEYS 1.
Performing the Smear Survey a) Instrumentation is. assembled, using the alpha probe, rate-meter, digital scaler unit, and the sample counting set up.
The instrumencs should be checked for proper operation (see References, 3.4).
b) The smear samples are taken, using paper or cloth smears (i.e., NUCON Si4 EARS).
c) The clean smear is removed from its backing and held on the tips of the fingers.
d) ' An area of approximately 100 cm is smeared by rubbing the surface in a 2
zig-zag pattern, approximately 6 inches long and 3 inches wide.
e) The smear is then carefully placed on an appropriately labeled smear folder and stored -(usually in an envelope) for counting at a later time. Care should be taken to not cross contaninate individual smears.
f) The locations, dates, time, etc., are noted in the survey log, appropriate survey form (Attachment 1), and on a map / diagram of the area.
g) After all the desired smears hav'e been made, preparation for counting can begin.
2.
Counting the smears a) Having previously assembled the appropriate instrumentation (Section 'a' above), background counts should be made prior to, or during the collection of the smear samples.
b) Smear samples are counted in the same manner as air samples. Refer to Appendix I, Section 2a through 2f.
~
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~
CENSE N0'.
37-13129-01 ATTAC! DIE'?T $ 7 (Con t ' d )
RR253AN85.KRC (Page.87 0F 89)
L(PAGE 160 0F 169)
- H 3.
Calculating the results The results are calculated as follows:
a)~ Calculating the M.D.L. (minimum detectable limit)
MDL = 5.54 x-total counts background
= C.P.M.
total count time background' 2
DPM (per 100 cm )*
=
=
(instrument counting efficiency)
- Since the area of the smear is approximately equal to the active 2
area of the probe, and the smear was taken over appros.mately 100 cm,
r the calculated OPM is read as per 100 cm,
b) Calculating the results of counting the smears.
(total counts-smear)
(total counts-background)
.= net C.P.M.-smear (total ct time-smear), (total ct time-background)
CPM "fg 2
D.P.H./100 cm * (see note, section 3a above)
=
(instrumentscountingefficiency) c) All results shall be entered on the appropriate survey form. (Attachment 1) 4 1
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L rENSE NO. 37-13129 RR25JAN85.NRC (PAGE 163 0F 169)-
ATTACHMENT $8
!Y#
/47 (Pase 1 0F 1)
SUMMARY
OF ITEM 11:
WASTE MANAGEMENT:
All Radioactive Waste ~is disposed in BCCordance With Procedure No. R-9(Section 7.0 WASTE DISPOSAL).
However, due to the present small volume of radioactive waste senerated 69 RMC's activities, the
(
.RSO will re-evaluate the need for disposal to the sanitarv sewase system in light of IE Information Notice No. 84-94.
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7(V L{^ NSE NO.- 3?-13:29-01 RFblJ AN85. NRC (PAGE 164 OF 169)
ATTACHMENT 99 (Pace 1 0F 1)
INFORMATION SPECIFIC TO MEDICAL SERVICES DIVISION USE AT 3508 AND 3440 NARNET STREET, PHILADELPHIA, PA.
19104.
(Use Address A.)
- tt*****************************************************************
A.
3503 harket Street:
The facilities at this address are essentitlly for emergency use oniv.
Thev would be used for the analvsis of Bioassav samples for clients of.our Emersency Medical Assistance Program (EMAP) in the.
event of an emergenev.
Some routine analvsis of Bioassav samples, other low activity samPlet and Calibration samples Will be Performed to assure the facility and eovipment are in a state of. readiness at all times.
The f acilities -might.also be used for possession, storase, etc. of other radioactive materials if RMC's senior authorized users (Linnemann, McGee, Bronson, Booth) Judsed it to be in a client's and/or the Public's interest to minimize (ALARA)
Potential damage / exposure in the event of an emergencv/ accident.
B.
3440 Market Street:
After the Nuclear Services Division (NERO) moves the Cs-137 Calibration Facility to Pottstown (amendment reauest Pendins),
the EMAP Bioassaw Laboratory Countins Room-and eouipment may be movec' into this facilitv.
In any event, the room will be retained by RMC for temporarv storase of isotopes and/or use in the event of an emersenew as indicated above.
- t********************************************************
r3 LICEf*T NO. 37-13129-01 U-RR25 U 85.NRC (PAGE 165 0F 169)
ATTACHNENT #10 (Pase 1 0F-1)
INFORMATION SPECIFIC TO NUCLEAR SERVICES DIVISION (MWRO)-USE AT 3356 COMMERCIAL AVENUE, NORTHBROOK, ILL.
60002.
(Use Address B.)
The Nuclear Services Division (HWRO) consists of a six room suite of lab space and offices located in a single level office building..The buildins is within'a ten acre industrial Park
. complex, with no residential ouarters within the-complex boundaries.
This of fice 'is Prima rilit involved in Construction, Calibration,-
operation and data interpretation related to Whole BodV Counting.
It also has a. mobile radiation detection laboratorw.and is involved in field radiation measurements related to D.
1 D. efforts.- Other Health Phwsics related services are also offered.
The licensed.~ material will be stored in shielded container (s) and cabinets (s) located within the.RMC auarters, so that the reouirement of Title 10 CFR Part 20, Section 20.105(10CFR 20.105) will be met for all locations in the building which are contisuous to the RHC ouarters.
Licensed materici will on1w be used in RMC's ouarters in a manner consistent with the reouirements of 10CFR 20.105).
Licensed materials will be kePt locked'when unattended to Prevent
. unauthorized removal.
The licensed material will be inventoried (beins Phwsicallw sighted) at least annuallw bw an authorized user.
A record of the most recent inventorv will be maintained for inspection bw RMC
' internal auditors and authorized.sovernment agents.
i The standards for Parmitting an individual to Work With radioactive materials wil1~be those listed below!
- The individual must demonstrate in the Performance of his work a level of knowledge and skill adeouate to insure Proper radiation safetw Practices.
- The individual must demonstrate a seneral familiaritu with the contents of 10 CFR Part 19 and Part 20 and the abilftv to use them as a reference.
l l
- The individual must demonstrate a working knowledge of our radioactive material license.
- The individual must demonstrate a general working knowledde l-of radiation safetw instruments.
i
- The individual must Perform satisfactorily in written and/or oral examination administered bw Lee Booth or Frazier Bronson.
l l
LICF(
NO. SNM-1524 6
RR01APR95.NRC (PAGE 144 0F 147) i ATTACHMENT *11 (Page 1 0F 1)
INFORMATION SPECIFIC TO NUCLEAR SERVICES DIVISION USE AT ONE STATE STREET, MERIDEN, CT.
(Use Address C.)
The Nuclear Services Divisiunt Heriden-Office, consists of several-offices ~ located within a office building owned 69 Canberra Industries, Inc.
Access /use of other facilities within the complex-is available to RMC Personnel includins lecture / training facilities, laboratories and test-facilities.
This office is Primarily involved in develoPhentt Construction and calibration activities related to Whole Bodv Counting.
The licensed material will be stored in appropriate 1V shielded /
locked cabinets (s) located within the RMC/ Canberra ouarters.
The licensed material will be inventoried (beind Physically sighted) at least annuallw by an authorized user.
A record of the most recent inventorv will be maintained for inspection bw RMC internal auditors and authorized sovernment agents.
The standards for Permitting an individuDI to Work with radioactive materials will be those listed below!
- The individual must demonstrate in the Perforkance of his work a level of knowledge and skill adeaua+.e to insure Prorer radiation safety practices.
- The individual must demonstrate a general familiarity with the cont'ents of 10 CFR Part 19 and Part 20 and the ability to use them as a reference.
- The individual must demonstrate a working knowledge of. our radioactive material license.
- The individual must demonstrate a seneral working knowledge of radiation safety instruments.
- The individual must Perform satisfactorilW in Written and/or oral examination administered bv Frazier Bronson or C.
E. He Dee.
t9NSE
- 70. 37-13129-01 Ifk25JAN85.NRC (PAGE 167 0F 169)
ATTACHNENT 012
!Y #
A7 (Pade 1 0F 1)
INFORMATION' SPECIFIC TO NUCLEAR SERVICES DIVISION (NERO) USE AT 1455 SCHUYLNILL ROAD (ROUIE 724),
POTTSTOWN, PA.
19464.
(Use Address
- C.).
The Nuclear Services Division (NERO) has moved its offices to the above address.
However, the 130 Ci Cs-137 source and other sources are still located at 3340 Market Street Pending approval of an Amendment Reouest submitted on 09-JAN-85 to move it and the other sources to the Pottstown address.
In addition to the Calibration Trailer (housins the Cs-137 source),
-one or more Whole Body Counters will be Parked in the Trailer Parkins Area when not in use.
This office offers a full ranse of Health Physics related~ services, including!
Licensing Assistance Radiation Instrument Calibrations and Repair Procedure Development Radiation Related Training Field Surveys Decontamination 1 Decommissioning General Health Physics Consulting O
I
n L(_]NSE NO. 37-13129-01 o
s_e RR2AJAN65.HRC (PAGE 168 0F 169)
ATTACHMENT *13 (Pase 1 0F 2)
INFORMATION. SPECIFIC TO TEMPORARY JOB SITES AND CUSTOMER FACILITIES.
(Use Address E.).
A.
GENERAL:
1.
The Possession, storase and use of licensed acterial at
~
customer locations shall be bv an RMC authorized user or an individual under the supervision of an RMC authori cd user.
On-site storase of RMC licensed material at customer locations SHALL be kept to the minimum amount feasible to complete the Job scope.
Should licensed material have to be kept at customer locations, adeouate erecautions SHALL be taken to prevent unauthorized use or removal.
Such precautions SHALL include, but are not limited to, lockins up
. licensed material to Prevent unauthorized use or removal when the authorized user is not Present.
2.
RMC Procedure No.
R-9,
' RADIATION PROTECTION PROCEDURE *, also applies to licensed material used at customer locations.
Reauirements of this procedure MUST be followed when workins at customer locations.
3.
In addition to comp 191ns with applicable RMC Procedures, Protocols, instructions, etc. involvins use of licensed mCteri~al or Performance of Job tasksi RMC Personnel WILL ALSO COMPLY with anw additional restrictions / radiation Protection Prcetices of the customer involved.
This item is especially important if the customer also has an NRC or Asreement State license.
B.
ROUTINE OPERATIONS:
1.
AT CUSTOMER LOCATIONS IN NON-AGREEMENT STATES:
a.
Notification /aPProvcl SHALL be obtained from the customer.
If the customer has an NRC license, approval SHALL be bv individuals authorized bw the customer and/or it's NRC license to make such approval.
b.
Such approval shall state as a minimum (1)
That the temPorarv Job is beins performed under appropriate provisions of the customer's and/or RNC's NRC license.
(2)
Anu limitations /renuirements for the temporarv Job relative to isotopes, isotopes forms, maximum activities *, isotope uses, isotope users, isotope storage, radiation survews, etc. and Job locations.
(I
^
/O m)
LLshSE HO. 37-13129-01 RR24JAN85.HRC (PAGE 169 0F 169)
ATTACHMENT 013(Cont'd)
(Pase 2.'0F 2)
INFORMATION SPECIFIC TO TEMPORARY JOB SITES AND~ CUSTOMER FACILITIES.
(Use Address E.).
- t*************3*t**********
2.
AT CUSTOMER LOCATION IN AGREEMENT STATES PROVIDED THAT1
- tt*******t************************************************
a.
A. license from the Agreement State is held by RMC or the customer or a Temporary Permit is obtained Prior to use of licensed material.
b.
All preceeding items of this Attachment are be followed to the fullest extent feasible, (i.e.
A.L.,
A.2.,
A.3.,
B.1.
and B.2.a.)
C.
EMERGENCY OPERATIONS:
1.
THIS CONDITION CAN ONLY BE INVOKED BY THE AUTHORIZED USERS LISTED UNDER 3A. AND 3B.
2.
Telephone notification to the appropriate NRC Regional Office i
and/or the impacted Asreement State SNALL be made BEFORE conmencement of EMERGENCY OPERATIONS.
3.
All proceeding items of this Attachment will be followed to the fullect extent feasible -- commensurate with the ALARA Philosophvil!
i
(
I e
0 l
rU b
$1 T
EET JEEN: Willia
- 0. Miller, Chief p(
License Fee Mar 2gement Branch Office of Administration J i
John E. Glenn. Chief Nucicar Materials Section 6 Division of Engineering and Technical Programs LICENSE rEE TRANSMITTAL A.
REGION /[
[-
1.
APPLICATION ATTACHED Applicant / Licensee:
Mdd t VhkQ Application Dated:
0362G Control No.:
bM-bN License No.:
k
.E.
FEE ATTACHED MO Anount:
d3W9 Check No.:
3.
CO W.ENTS Signed k~hf Date y//g N
B.
LICENSE FEE MANAGEMENT BRANCH k
3bD 1.
Fee Category and Amount:
I 2.
Correct fee Paid.
Application ruy be processed for:
Ar.endment Renewal
/
License Signed tA9 h
4/usisd u
Oate I
V(,
')
- l. /
REGION I FORM 213 (PARCH 1983)
J